diff --git a/icsbep/README.md b/icsbep/README.md new file mode 100644 index 0000000..bb3a4be --- /dev/null +++ b/icsbep/README.md @@ -0,0 +1,18 @@ +# Instructions for MC/DC's ICSBEP validation suite + +This continuous energy criticality validation test suite is taken from OpenMC's benchmark repository: https://github.com/mit-crpg/benchmarks/tree/master/icsbep + +It contains several hundred criticality problems from the international criticality safety benchmark evaluation project (ICSBEP). Currently only 118 of them translate and run with the current state of the translator. + + +## Running problems: + +Inside the icsbep directory, the icsbep_translator.ipynb file is a slightly modified version of the OpenMC to MC/DC xml translator found in the CEMeNT organization's repositories (may be private). + +There is also an openmc directory which houses all the folders for the input decks and the bash scripts to run them. Inside each problem directory, an openmc directory has subdirectories for each case, and an mcdc directory places all the translated input files in a single place. + +Inside the base icsbeb/openmc directory, there are two bash scripts: run_mcdc.sh and run_openmc.sh. These should scan all subdirectories, create slurm submission scripts for each input deck, and submit those decks to the pbatch partition. Please note that this has been set up for LLNL's Dane machine, and each of these input scripts will need to be customized to the user. + +The python script collect_results.py will scan those subdirectories and scrape the keff results for both codes. + +Also note that OpenMC's default submission scripts have been left in, but they will not work for MC/DC or on LLNL's systems. diff --git a/icsbep/icsbep_translator.ipynb b/icsbep/icsbep_translator.ipynb new file mode 100644 index 0000000..e2a6418 --- /dev/null +++ b/icsbep/icsbep_translator.ipynb @@ -0,0 +1,1159 @@ +{ + "cells": [ + { + "cell_type": "code", + "execution_count": 1, + "metadata": {}, + "outputs": [], + "source": [ + "import lxml.etree as et\n", + "from lxml import etree\n", + "import numpy as np\n", + "import h5py, os, sys\n", + "\n", + "try:\n", + " import openmc\n", + "except ImportError:\n", + " None\n", + "\n", + "AVAGADRO = 6.02214076e23" + ] + }, + { + "cell_type": "code", + "execution_count": 2, + "metadata": {}, + "outputs": [], + "source": [ + "# Additional Functions Relating to Materials_XML_Parser\n", + "def Atomic_Mass(Nuc): # Temp Solution, simplifies to the Atomic Mass Number\n", + " # Pulls Data from the NIST Nuclude Data file if it exists\n", + " if os.path.exists(\"nist-nuclide-data.txt\"):\n", + " Symbol = \"\"\n", + " Mass_Num = \"\"\n", + " for _ in Nuc:\n", + " try:\n", + " int(_)\n", + " Mass_Num += _\n", + " except:\n", + " Symbol += _\n", + " Mass_Num = int(Mass_Num)\n", + " NAT_AB = False\n", + " if Symbol == \"H\":\n", + " if Mass_Num == 2:\n", + " Symbol = \"D\"\n", + " elif Mass_Num == 3:\n", + " Symbol = \"T\"\n", + " if any([_ == Symbol for _ in [\"C\", \"Zn\", \"Pt\", \"Os\", \"Tl\"]]) and Mass_Num == 0:\n", + " NAT_AB = True\n", + " with open(\"nist-nuclide-data.txt\", \"r\") as Data:\n", + " Data_Lines = Data.readlines()[:]\n", + " for n, line in enumerate(Data_Lines):\n", + " if line[16:-1] == Symbol:\n", + " if int(Data_Lines[n + 1][14:-1]) == Mass_Num:\n", + " AM = float(Data_Lines[n + 2][23:-1].split(\"(\")[0])\n", + " break\n", + " elif NAT_AB:\n", + " AM = float(Data_Lines[n + 4][25:-1].split(\"(\")[0])\n", + " break\n", + " Data_Lines.clear()\n", + " # Runs OpenMC function if NIST data does not exist and OpenMC module is installed\n", + " elif \"openmc\" in sys.modules:\n", + " AM = openmc.atomic_mass(Nuc)\n", + " # Approximates atomic mass to atomic mass number (int) if either other method fails\n", + " else:\n", + " AM = \"\"\n", + " for _ in Nuc:\n", + " try:\n", + " AM += str(int(_))\n", + " except:\n", + " None\n", + " AM = int(AM)\n", + " print(\n", + " f\"WARNING: Using integer approximation for {Nuc}.\\nEnsure nist-nuclide-data.txt or OpenMC are available.\"\n", + " )\n", + " return AM\n", + "\n", + "\n", + "def Average_Molar_Mass(Material=[], Percent=[], Percent_Type=[]):\n", + " # Fuction pulled from OpenMC, calculates avg molar mass based on nuclide composition\n", + " mass = 0\n", + " moles = 0\n", + " assert len(Material) == len(Percent_Type) == len(Percent)\n", + " for i in range(len(Material)):\n", + " if Percent_Type[i] == \"ao\":\n", + " mass += Percent[i] * Atomic_Mass(Material[i])\n", + " moles += Percent[i]\n", + " elif Percent_Type[i] == \"wo\":\n", + " mass += Percent[i]\n", + " moles += Percent[i] / Atomic_Mass(Material[i])\n", + " return mass / moles\n", + "\n", + "\n", + "def Reconstruct_Scatter_Matrix(Data=dict()):\n", + " # Method only works if Scatter Data is saved properly by OpenMC cross sections file\n", + " Flat_Scatter = np.array(\n", + " Data[\"scatter_data\"][\"scatter_matrix\"]\n", + " ) # Pulls Mx1 scatter data\n", + " g_min = (\n", + " np.array(Data[\"scatter_data\"][\"g_min\"]) - 1\n", + " ) # Determines min group number of rows\n", + " g_max = (\n", + " np.array(Data[\"scatter_data\"][\"g_max\"]) - 1\n", + " ) # Determines max group number of rows\n", + " Num_Groups = len(g_min)\n", + " Scatter_Matrix = np.zeros([Num_Groups, Num_Groups])\n", + " for i in range(Num_Groups):\n", + " N = g_max[i] - g_min[i] + 1 # Defines N values to pull from Mx1 scatter data\n", + " Scatter_Matrix[i, g_min[i] : g_max[i] + 1] = Flat_Scatter[\n", + " :N\n", + " ] # Fills GxG matrix from min to max of row i\n", + " Flat_Scatter = np.delete(Flat_Scatter, range(N)) # Removes used data\n", + " Scatter_Matrix = np.transpose(\n", + " Scatter_Matrix\n", + " ) # Proper formatting for Scatter Matrix\n", + " return Scatter_Matrix" + ] + }, + { + "cell_type": "code", + "execution_count": 3, + "metadata": {}, + "outputs": [], + "source": [ + "# Additional Functions Relating to Geometry_XML_Parser\n", + "def Region_Fill(py_file=None, Cell=dict()):\n", + " if py_file == None:\n", + " py_file = open(\"_.py\", \"t+a\")\n", + " Regions = Cell.get(\"region\")\n", + " if Regions != None:\n", + " Region_IDs = np.array([val for val in Regions.split()])\n", + " # py_file.write(\"region=\") # Temporarily removed in case of redundancy\n", + " else:\n", + " return # Exits function if cell has no regions\n", + "\n", + " Skip = True\n", + " for i in range(len(Region_IDs)):\n", + " Region_ID = Region_IDs[i]\n", + " # Runs through CSG operators, skips '&' for '|', continues if left blank\n", + " if not Skip and Region_ID[0] != \"|\":\n", + " py_file.write(\" & \")\n", + " if Region_ID[0] == \"~\":\n", + " py_file.write(\"~\")\n", + " Region_ID = Region_ID[1:]\n", + " elif Region_ID[0] == \"|\":\n", + " py_file.write(\" | \")\n", + " Region_ID = Region_ID[1:]\n", + " Skip = False\n", + " if Region_ID == \"\":\n", + " Skip = True\n", + " continue\n", + " # Looks for parathesis goruping and ensures only ID int remains\n", + " while type(Region_ID) == str or type(Region_ID) == np.str_:\n", + " if Region_ID[0] == \"(\":\n", + " py_file.write(\"(\")\n", + " Region_ID = Region_ID[1:]\n", + " if Region_ID[-1] == \")\":\n", + " close_join += 1\n", + " Region_ID = Region_ID[:-1]\n", + " else:\n", + " close_join = 0\n", + " try:\n", + " Region_ID = int(Region_ID)\n", + " except:\n", + " None\n", + " # Applys + or - half-spaces, then writes surface into region\n", + " if Region_ID > 0:\n", + " r_sign = \"+\"\n", + " elif Region_ID < 0:\n", + " r_sign = \"-\"\n", + " py_file.write(f\"{r_sign}s{int(abs(Region_ID))}\")\n", + " py_file.write(close_join * \")\") # Closes grouped and subgrouped regions\n", + " py_file.write(\", \")\n", + " if py_file.name == \"_.py\":\n", + " py_file.close()\n", + "\n", + "\n", + "def Write_Universes(\n", + " Geom_Root,\n", + " py_file,\n", + " Lat_ID=None,\n", + " Complex=False,\n", + " Exclude_List=None,\n", + " Defined_Cells=None,\n", + "):\n", + " global created_universes\n", + "\n", + " Univ_Data = np.array([[0, 0]])\n", + " Written_Universes = []\n", + " for Cell in Geom_Root.findall(\"cell\"):\n", + " if (\n", + " Cell.get(\"material\") != None and Lat_ID == None and not Complex\n", + " ): # Pulls material universes\n", + " Univ_ID = int(Cell.get(\"universe\"))\n", + " Cell_ID = int(Cell.get(\"id\"))\n", + " Univ_Data = np.append(Univ_Data, np.array([[Univ_ID, Cell_ID]]), axis=0)\n", + " elif (\n", + " Cell.get(\"fill\") != None and Lat_ID == None and Complex\n", + " ): # Pulls complex universes that are not excluded\n", + " if int(Cell.get(\"fill\")) in Exclude_List:\n", + " continue\n", + " Univ_ID = int(Cell.get(\"universe\"))\n", + " Cell_ID = int(Cell.get(\"id\"))\n", + " Univ_Data = np.append(Univ_Data, np.array([[Univ_ID, Cell_ID]]), axis=0)\n", + " elif Cell.get(\"fill\") == str(Lat_ID): # Pulls lattice univere with specified ID\n", + " Univ_ID = int(Cell.get(\"universe\"))\n", + " Cell_ID = int(Cell.get(\"id\"))\n", + " Univ_Data = np.append(Univ_Data, np.array([[Univ_ID, Cell_ID]]), axis=0)\n", + " if Univ_Data.shape != (1, 2):\n", + " # Constructs Univsere dictionary grouping cell IDs to Universe IDs\n", + " Univ_Data = np.delete(Univ_Data, 0, 0).T\n", + " Univ_Dict = {\n", + " n: rep[n]\n", + " for rep in [{}]\n", + " for i, n in enumerate(Univ_Data[0, :])\n", + " if rep.setdefault(n, []).append(i) or len(rep[n]) == 1\n", + " }\n", + " for key in Univ_Dict:\n", + " if Complex:\n", + " if not all(\n", + " [\n", + " (_ in Defined_Cells)\n", + " for _ in [Univ_Data[1, i] for i in Univ_Dict[key]]\n", + " ]\n", + " ):\n", + " continue\n", + "\n", + " if (\n", + " key not in created_universes\n", + " ): # If u# is not already defined, it creates u# with initial cells\n", + " py_file.write(f\"u{key} = mcdc.universe([\")\n", + " created_universes.append(key)\n", + " else: # If u# was already defined, uses u#.add_cells with new cells\n", + " py_file.write(f\"u{key}.add_cells([\")\n", + " for j, i in enumerate(Univ_Dict[key]):\n", + " py_file.write(f\"c{Univ_Data[1,i]}\")\n", + " if i != Univ_Dict[key][-1]:\n", + " py_file.write(\", \")\n", + " if j % 20 == 19:\n", + " py_file.write(\n", + " \"\\n\\t\\t\"\n", + " ) # Moves to next line if there are more than 20 cells/line, compacts formatting\n", + " if (key == 0) and (key not in created_universes):\n", + " py_file.write(\n", + " \"], root=True])\\n\"\n", + " ) # If OpenMC uses universe 0 as root, sets u0 as the root universe\n", + " else:\n", + " py_file.write(\"])\\n\")\n", + " Written_Universes.append(int(key))\n", + "\n", + " return Written_Universes\n", + "\n", + "\n", + "def Write_Rect_Lattice(Lattice, py_file, Lat_ID=None):\n", + " # Creates lattice configuration for 1D, 2D, or 3D rectangular lattices, Hexagonal lattices not implemented yet.\n", + " # Identifies individual lattices based on Lat_ID\n", + " py_file.write(f\"\\n# Rectangular Lattice {Lat_ID}\\n\")\n", + " if Lattice.get(\"name\") != None:\n", + " py_file.write(f\"# Name: {Lattice.get('name')}\\n\")\n", + " py_file.write(f\"Lattice{Lat_ID} = mcdc.lattice(\")\n", + " dims = np.array([int(val) for val in Lattice.find(\"dimension\").text.split()])\n", + " pitch = np.array([float(val) for val in Lattice.find(\"pitch\").text.split()])\n", + " Lower_Left = np.array(\n", + " [float(val) for val in Lattice.find(\"lower_left\").text.split()]\n", + " )\n", + " xyz_str = [\"x\", \"y\", \"z\"]\n", + " for i in range(len(pitch)):\n", + " py_file.write(\n", + " \"{}=[{}, {}, {}], \".format(xyz_str[i], Lower_Left[i], pitch[i], dims[i])\n", + " )\n", + " # Pulls lattice str from xml and reformats into desired shape based on dimensions\n", + " Lattice_xml = np.array(Lattice.find(\"universes\").text.split(\"\\n\"))\n", + " Lattice_xml = np.delete(Lattice_xml, np.where(Lattice_xml == \"\"))\n", + " Lattice_xml = np.array([ind.split() for ind in Lattice_xml]).flat\n", + " Lattice_xml = np.delete(Lattice_xml, np.where(Lattice_xml == \"\")).astype(int)\n", + " Lattice_Fin = np.reshape(Lattice_xml, dims[::-1])\n", + "\n", + " # Fills in universes, determines positions for [ and ] and seperates into lines matching shape\n", + " py_file.write(f\"universes=\" + (len(dims) - 1) * \"[\")\n", + " if len(dims) == 2:\n", + " dims = np.append(dims, 1)[::-1]\n", + " Lattice_Fin = np.reshape(Lattice_Fin, dims)\n", + " else:\n", + " dims = dims[::-1]\n", + " for i in range(dims[0]):\n", + " for j in range(dims[1]):\n", + " py_file.write(\"\\n\\t[\")\n", + " for k in range(dims[2]):\n", + " py_file.write(\"u{}\".format(Lattice_Fin[i, j, k]))\n", + " if k != dims[2] - 1:\n", + " py_file.write(\", \")\n", + " py_file.write(\"]\")\n", + " if j != dims[1] - 1:\n", + " py_file.write(\",\")\n", + " if i != dims[0] - 1:\n", + " py_file.write(\"],[\")\n", + " py_file.write((len(pitch) - 1) * \"]\" + \")\\n\")\n", + "\n", + "\n", + "def Convert_Setting_Value(Sett_Val=None):\n", + " # Tests if Sett_Val is bool arg as string\n", + " if Sett_Val == \"true\":\n", + " Sett_Val = True\n", + " elif Sett_Val == \"false\":\n", + " Sett_Val = False\n", + " # Tests and corrects if Sett_Val is an int or float value\n", + " else:\n", + " try:\n", + " Sett_Val = float(Sett_Val)\n", + " except:\n", + " None # Val is str\n", + " try:\n", + " Sett_Val = int(Sett_Val)\n", + " except:\n", + " None # Val is str or float\n", + " # Otherwise returns str as it was initially input\n", + " return Sett_Val\n" + ] + }, + { + "cell_type": "code", + "execution_count": 4, + "metadata": {}, + "outputs": [], + "source": [ + "\n", + "# XML Parser/Translator Functions\n", + "def Materials_XML_Parser(XML_file=\"materials.xml\", py_file=None):\n", + " \"\"\"Sub-parcer for materials\n", + "\n", + " .. version:: 0.1.5\n", + "\n", + " \"\"\"\n", + "\n", + " if py_file == None:\n", + " py_file = open(\"Materials_Only.py\", \"t+w\")\n", + " py_file.write(\"import mcdc\\nimport numpy as np\\n\\n\")\n", + " else:\n", + " py_file.write(\n", + " \"\\n\" + 30 * \"#\" + \"\\n#__________Materials__________\\n\" + 30 * \"#\" + \"\\n\\n\"\n", + " )\n", + " Mats_Parse = et.parse(XML_file)\n", + " Mats_Root = Mats_Parse.getroot()\n", + " if Mats_Root.tag == \"model\":\n", + " Mats_Root = Mats_Root.find(\"materials\")\n", + "\n", + " if Mats_Root.find(\"cross_sections\") != None:\n", + " MXS_File = h5py.File(Mats_Root.find(\"cross_sections\").text, \"r\")\n", + "\n", + " # Create MC/DC MGXS\n", + " file_name = \"mcdc-\" + Mats_Root.find(\"cross_sections\").text\n", + " with h5py.File(file_name, \"w\") as f:\n", + " for material in list(MXS_File.keys()):\n", + " for temperature in list(MXS_File[material].keys()):\n", + " if temperature == \"kTs\":\n", + " continue\n", + "\n", + " name = material + \"-\" + temperature + \"/\"\n", + " data = MXS_File[material][temperature]\n", + "\n", + " total = data[\"total\"][:]\n", + " G = len(total)\n", + "\n", + " fission = np.zeros(G)\n", + " nu = np.zeros(G)\n", + " chi = np.zeros((G, G))\n", + "\n", + " if \"fission\" in list(data.keys()):\n", + " fission = data[\"fission\"][:]\n", + " nu_fission = data[\"nu-fission\"][:]\n", + " nu = nu_fission / fission\n", + "\n", + " chi_1d = data[\"chi\"][:]\n", + " for g in range(G):\n", + " chi[g, :] = chi_1d[g]\n", + "\n", + " absorption = data[\"absorption\"][:]\n", + " capture = absorption - fission\n", + " scatter = Reconstruct_Scatter_Matrix(data)\n", + "\n", + " f.create_dataset(name + \"capture\", data=capture)\n", + " f.create_dataset(name + \"fission\", data=fission)\n", + " f.create_dataset(name + \"scatter\", data=scatter)\n", + " f.create_dataset(name + \"nu\", data=nu)\n", + " f.create_dataset(name + \"chi\", data=chi)\n", + "\n", + " py_file.write(\n", + " f\"import h5py\\nMXS_Lib = h5py.File('mcdc-{Mats_Root.find('cross_sections').text}')\\n\"\n", + " )\n", + "\n", + " for Mat in Mats_Root.findall(\"material\"):\n", + " Mat_ID = int(Mat.get(\"id\"))\n", + " Mat_name = Mat.get(\"name\")\n", + " if Mat_name != None:\n", + " py_file.write(f\"# Material Name: {Mat_name}\\n\")\n", + " if Mat.get(\"temperature\") != None:\n", + " py_file.write(f\"# Temperature: {Mat.get('temperature')}K\\n\")\n", + " if Mat.find(\"sab\") != None:\n", + " for Sab in Mat.findall(\"sab\"):\n", + " Sab_name = Sab.get(\"name\")\n", + " py_file.write(f\"# S(a,b): {Sab_name} (Not Implemented)\\n\")\n", + " if Mat.get(\"depletable\") != None:\n", + " py_file.write(\"# Depletable\\n\")\n", + "\n", + " density_units = Mat.find(\"density\").get(\"units\")\n", + " sum_density = False\n", + " MACRO_Pull = False\n", + " if density_units != \"sum\" and density_units != \"macro\":\n", + " density = float(Mat.find(\"density\").get(\"value\"))\n", + " if density_units == \"g/cm3\" or density_units == \"g/cc\":\n", + " density *= 1\n", + " den_in_atom = False\n", + " elif density_units == \"kg/m3\":\n", + " density *= 0.001\n", + " den_in_atom = False\n", + " elif density_units == \"atom/barn-cm\":\n", + " density *= 1\n", + " den_in_atom = True\n", + " elif density_units == \"atom/cm3\" or density_units == \"atom/cc\":\n", + " density *= 1.0e-24\n", + " den_in_atom = True\n", + " elif density_units == \"sum\":\n", + " sum_density = True\n", + " den_in_atom = True\n", + " density = 0\n", + " elif density_units == \"macro\":\n", + " MACRO_Pull = True\n", + "\n", + " if not MACRO_Pull:\n", + " Nuc_Names = np.array([])\n", + " Nuc_Den_Values = np.array([])\n", + " Nuc_Den_Types = np.array([])\n", + " for Nuc in Mat.findall(\"nuclide\"):\n", + " Nuc_Names = np.append(Nuc_Names, Nuc.get(\"name\"))\n", + " if Nuc.get(\"ao\") != None:\n", + " Nuc_Den_Values = np.append(Nuc_Den_Values, float(Nuc.get(\"ao\")))\n", + " Nuc_Den_Types = np.append(Nuc_Den_Types, \"ao\")\n", + " elif Nuc.get(\"wo\") != None:\n", + " Nuc_Den_Values = np.append(Nuc_Den_Values, float(Nuc.get(\"wo\")))\n", + " Nuc_Den_Types = np.append(Nuc_Den_Types, \"wo\")\n", + " else:\n", + " print(\"No type\")\n", + " AVG_Molar_Mass = Average_Molar_Mass(\n", + " Nuc_Names, Nuc_Den_Values, Nuc_Den_Types\n", + " )\n", + " percent_in_atom = np.all(Nuc_Den_Types == \"ao\")\n", + "\n", + " if sum_density:\n", + " density = np.sum(Nuc_Den_Values)\n", + " if not percent_in_atom:\n", + " for n, nuc in enumerate(Nuc_Names):\n", + " Nuc_Den_Values[n] *= AVG_Molar_Mass / Atomic_Mass(nuc)\n", + " sum_percent = np.sum(Nuc_Den_Values)\n", + " Nuc_Den_Values /= sum_percent\n", + " if not den_in_atom:\n", + " density *= AVAGADRO / AVG_Molar_Mass * 1e-24\n", + " Nuc_Den_Values *= density\n", + "\n", + " py_file.write(f\"m{Mat_ID} = mcdc.material(\")\n", + " py_file.write(\"nuclides=[\\n\")\n", + " for i in range(len(Nuc_Names)):\n", + " if Nuc_Names[i] == \"U234\" or Nuc_Names[i] == \"Th232\" or Nuc_Names[i] == \"Pu241\" or Nuc_Names[i] == \"U236\":\n", + " continue\n", + " if Nuc_Names[i] == \"C0\":\n", + " Nuc_Names[i] == \"C12\"\n", + " py_file.write(f\"\\t['{Nuc_Names[i]}',{Nuc_Den_Values[i]}]\")\n", + " if Nuc_Names[i] != Nuc_Names[-1]:\n", + " py_file.write(\",\\n\")\n", + " else:\n", + " py_file.write(\"])\\n\")\n", + "\n", + " elif MACRO_Pull:\n", + " py_file.write(f\"# Cross-sections From: mcdc-{MXS_File.filename}\\n\")\n", + " Mat_Key = Mat.find(\"macroscopic\").get(\"name\")\n", + " OpenMC_SubKey = list(MXS_File[Mat_Key].keys())[0]\n", + " py_file.write(f\"M{Mat_ID}_Lib = MXS_Lib['{Mat_Key}-{OpenMC_SubKey}']\\n\")\n", + " py_file.write(f\"m{Mat_ID} = mcdc.material(\\n\")\n", + " py_file.write(f\"capture = M{Mat_ID}_Lib['capture'],\\n\")\n", + " py_file.write(f\"scatter = M{Mat_ID}_Lib['scatter'],\\n\")\n", + " py_file.write(f\"fission = M{Mat_ID}_Lib['fission'],\\n\")\n", + " py_file.write(f\"nu_p = M{Mat_ID}_Lib['nu'],\\n\")\n", + " py_file.write(f\"chi_p = M{Mat_ID}_Lib['chi'],\\n\")\n", + " py_file.write(f\")\\n\")\n", + "\n", + " py_file.write(f\"mvoid = mcdc.material(nuclides=[['N14',1e-10]])\")\n", + " if Mats_Root.find(\"cross_sections\") != None:\n", + " MXS_File.close()\n", + " py_file.write(\"MXS_Lib.close()\\n\")\n", + "\n", + " if py_file.name == \"Materials_Only.py\":\n", + " py_file.close()\n", + " print(f\"Materials MCDC File: ./{py_file.name}\")\n", + " return" + ] + }, + { + "cell_type": "code", + "execution_count": 5, + "metadata": {}, + "outputs": [], + "source": [ + "created_universes = []" + ] + }, + { + "cell_type": "code", + "execution_count": 6, + "metadata": {}, + "outputs": [], + "source": [ + "\n", + "def Geometry_XML_Parser(XML_file=\"geometry.xml\", py_file=None):\n", + " \"\"\"Subparcer for geometry\n", + "\n", + " .. version:: 0.1.4\n", + "\n", + " \"\"\"\n", + "\n", + " if py_file == None:\n", + " py_file = open(\"Geometry_Only.py\", \"t+w\")\n", + " py_file.write(\"import mcdc\\n\\n\")\n", + " else:\n", + " py_file.write(\n", + " \"\\n\" + 30 * \"#\" + \"\\n#__________Geometry__________\\n\" + 30 * \"#\" + \"\\n\\n\"\n", + " )\n", + " Geom_Parse = et.parse(XML_file)\n", + " Geom_Root = Geom_Parse.getroot()\n", + " if Geom_Root.tag == \"model\":\n", + " Geom_Root = Geom_Root.find(\"geometry\")\n", + "\n", + " py_file.write(\"# Surface(s)\\n\")\n", + " for Surf in Geom_Root.findall(\"surface\"):\n", + " Surf_ID = int(Surf.get(\"id\"))\n", + " Surf_type = Surf.get(\"type\")\n", + " Surf_Coeffs = [float(val) for val in Surf.get(\"coeffs\").split()]\n", + " py_file.write(\"s{} = mcdc.surface(\".format(Surf_ID))\n", + "\n", + " # PLANE GEOMETRY\n", + " if Surf_type == \"x-plane\":\n", + " Surf_type = \"plane-x\"\n", + " py_file.write(\"'{}', x={f[0]}, \".format(Surf_type, f=Surf_Coeffs))\n", + " elif Surf_type == \"y-plane\":\n", + " Surf_type = \"plane-y\"\n", + " py_file.write(\"'{}', y={f[0]}, \".format(Surf_type, f=Surf_Coeffs))\n", + " elif Surf_type == \"z-plane\":\n", + " Surf_type = \"plane-z\"\n", + " py_file.write(\"'{}', z={f[0]}, \".format(Surf_type, f=Surf_Coeffs))\n", + " elif Surf_type == \"plane\":\n", + " py_file.write(\n", + " \"'{}', A={f[0]}, B={f[1]}, C={f[2]}, D={f[3]}, \".format(\n", + " Surf_type, f=Surf_Coeffs\n", + " )\n", + " )\n", + " # CYLINDER GEOMETRY\n", + " elif Surf_type == \"x-cylinder\":\n", + " Surf_type = \"cylinder-x\"\n", + " py_file.write(\n", + " \"'{}', center=[{f[0]}, {f[1]}], radius={f[2]}, \".format(\n", + " Surf_type, f=Surf_Coeffs\n", + " )\n", + " )\n", + " elif Surf_type == \"y-cylinder\":\n", + " Surf_type = \"cylinder-y\"\n", + " py_file.write(\n", + " \"'{}', center=[{f[0]}, {f[1]}], radius={f[2]}, \".format(\n", + " Surf_type, f=Surf_Coeffs\n", + " )\n", + " )\n", + " elif Surf_type == \"z-cylinder\":\n", + " Surf_type = \"cylinder-z\"\n", + " py_file.write(\n", + " \"'{}', center=[{f[0]}, {f[1]}], radius={f[2]}, \".format(\n", + " Surf_type, f=Surf_Coeffs\n", + " )\n", + " )\n", + " # SPHERE GEOMETRY\n", + " elif Surf_type == \"sphere\":\n", + " py_file.write(\n", + " \"'{}', center=[{f[0]}, {f[1]}, {f[2]}], radius={f[3]}, \".format(\n", + " Surf_type, f=Surf_Coeffs\n", + " )\n", + " )\n", + " # QUADRIC DEFINED GEOMETRY\n", + " elif Surf_type == \"quadric\":\n", + " py_file.write(\n", + " \"'{}', A={f[0]}, B={f[1]}, C={f[2]}, D={f[3]}, E={f[4]}, F={f[5]}, G={f[6]}, H={f[7]}, I={f[8]}, J={f[9]}, \".format(\n", + " Surf_type, f=Surf_Coeffs\n", + " )\n", + " )\n", + " elif Surf_type == \"x-cone\":\n", + " Surf_type = \"quadric\"\n", + " R2 = -Surf_Coeffs[3]\n", + " G = -2 * R2 * Surf_Coeffs[0]\n", + " H = -2 * Surf_Coeffs[1]\n", + " I = -2 * Surf_Coeffs[2]\n", + " J = R2 * Surf_Coeffs[0] ** 2 + Surf_Coeffs[1] ** 2 + Surf_Coeffs[2] ** 2\n", + " py_file.write(\n", + " f\"'{Surf_type}', A={R2}, B=1, C=1, G={G}, H={H}, I={I}, J={J}, \"\n", + " )\n", + " elif Surf_type == \"y-cone\":\n", + " Surf_type = \"quadric\"\n", + " R2 = -Surf_Coeffs[3]\n", + " G = -2 * Surf_Coeffs[0]\n", + " H = -2 * R2 * Surf_Coeffs[1]\n", + " I = -2 * Surf_Coeffs[2]\n", + " J = Surf_Coeffs[0] ** 2 + R2 * Surf_Coeffs[1] ** 2 + Surf_Coeffs[2] ** 2\n", + " py_file.write(\n", + " f\"'{Surf_type}', A=1, B={R2}, C=1, G={G}, H={H}, I={I}, J={J}, \"\n", + " )\n", + " elif Surf_type == \"z-cone\":\n", + " Surf_type = \"quadric\"\n", + " R2 = -Surf_Coeffs[3]\n", + " H = -2 * Surf_Coeffs[0]\n", + " I = -2 * Surf_Coeffs[1]\n", + " G = -2 * R2 * Surf_Coeffs[2]\n", + " J = Surf_Coeffs[0] ** 2 + Surf_Coeffs[1] ** 2 + R2 * Surf_Coeffs[2] ** 2\n", + " py_file.write(\n", + " f\"'{Surf_type}', A=1, B=1, C={R2}, G={G}, H={H}, I={I}, J={J}, \"\n", + " )\n", + " # Note: General Cone in OpenMC is saved as a quadric\n", + " # NOT TRANSLATABLE GEOMETRY (Torus)\n", + " else:\n", + " py_file.write(f\")# {Surf_type} not supported\")\n", + "\n", + " Surf_Bound = Surf.get(\"boundary\")\n", + " if Surf_Bound == None or Surf_Bound == \"transmission\":\n", + " bc = \"interface\"\n", + " elif Surf_Bound == \"reflective\" or Surf_Bound == \"white\":\n", + " bc = \"reflective\"\n", + " elif Surf_Bound == \"vacuum\":\n", + " bc = \"vacuum\"\n", + " else:\n", + " print(\"Boundary condition not accepted, defaulted to interface\")\n", + " bc = \"interface\"\n", + " py_file.write(f\"bc='{bc}')\")\n", + "\n", + " if Surf.get(\"name\") != None:\n", + " py_file.write(f\" # Name: {Surf.get('name')}\\n\")\n", + " else:\n", + " py_file.write(\"\\n\")\n", + "\n", + " Written_Cells = []\n", + " py_file.write(\"\\n# Material Cell(s)\\n\")\n", + " for Cell in Geom_Root.findall(\"cell\"):\n", + " if Cell.get(\"material\") == None:\n", + " continue\n", + " Cell_ID = int(Cell.get(\"id\"))\n", + " Written_Cells.append(Cell_ID)\n", + "\n", + " py_file.write(\"c{} = mcdc.cell(\".format(Cell_ID))\n", + " Region_Fill(py_file=py_file, Cell=Cell)\n", + " py_file.write(f\"fill=\")\n", + "\n", + " Mat_IDs = np.array([val for val in Cell.get(\"material\").split()])\n", + " for i in range(len(Mat_IDs)):\n", + " py_file.write(f\"m{Mat_IDs[i]}\")\n", + " if Mat_IDs[i] != Mat_IDs[-1]:\n", + " py_file.write(\", \")\n", + " py_file.write(\")\")\n", + "\n", + " if Cell.get(\"name\") != None:\n", + " py_file.write(f\" # Name: {Cell.get('name')}\\n\")\n", + " else:\n", + " py_file.write(f\"\\n\")\n", + "\n", + " py_file.write(\"# Root Universe Cells List:\\nu0_cells = []\\n\")\n", + " py_file.write(\"# Material Universe(s)\\n\")\n", + " # FIX: this line needs to be present for universes\n", + " # Written_Universes = Write_Universes(Geom_Root, py_file)\n", + "\n", + " Lat_IDs_List = []\n", + " for Lattice in Geom_Root.findall(\"lattice\"):\n", + " Lat_IDs_List.append(int(Lattice.get(\"id\")))\n", + "\n", + " Exclude_List = Lat_IDs_List.copy()\n", + " Writing_Complex = True\n", + " Level = 1\n", + "\n", + " while Writing_Complex:\n", + " if len(Geom_Root.findall(\"cell\")) == (len(Written_Cells) + len(Lat_IDs_List)):\n", + " Writing_Complex = False\n", + " continue\n", + " py_file.write(f\"\\n# Complex Cell(s) Level {Level}\\n\")\n", + " for Cell in Geom_Root.findall(\"cell\"):\n", + " if Cell.get(\"fill\") == None:\n", + " continue\n", + " Fill_ID = int(Cell.get(\"fill\"))\n", + " if not (Fill_ID in Exclude_List) and (Fill_ID in Written_Universes):\n", + " Cell_ID = int(Cell.get(\"id\"))\n", + " Written_Cells.append(Cell_ID)\n", + "\n", + " py_file.write(\"c{} = mcdc.cell(\".format(Cell_ID))\n", + "\n", + " Region_Fill(py_file=py_file, Cell=Cell)\n", + " py_file.write(f\"fill=u{Fill_ID}\")\n", + "\n", + " if Cell.get(\"translation\") is not None:\n", + " tr = Cell.get(\"translation\").split()\n", + " py_file.write(f\", translation=[{tr[0]}, {tr[1]}, {tr[2]}]\")\n", + "\n", + " if Cell.get(\"rotation\") is not None:\n", + " rot = Cell.get(\"rotation\").split()[0]\n", + " py_file.write(f\", rotation=[{rot[0]}, {rot[1]}, {rot[2]}]\")\n", + "\n", + " py_file.write(\")\")\n", + "\n", + " if Cell.get(\"name\") != None:\n", + " py_file.write(f\" # Name: {Cell.get('name')}\\n\")\n", + " else:\n", + " py_file.write(f\"\\n\")\n", + " py_file.write(f\"# Complex Universe(s) Level {Level}\\n\")\n", + " Complex_Universes = Write_Universes(\n", + " Geom_Root,\n", + " py_file,\n", + " Complex=True,\n", + " Exclude_List=Exclude_List,\n", + " Defined_Cells=Written_Cells,\n", + " )\n", + " Exclude_List = Lat_IDs_List + Written_Universes\n", + " Written_Universes += Complex_Universes\n", + " if len(Complex_Universes) == 0:\n", + " Writing_Complex = False\n", + " else:\n", + " Level += 1\n", + "\n", + " for Lattice in Geom_Root.findall(\n", + " \"lattice\"\n", + " ): # Update so that if universe is redefefined, it is instead updated\n", + " Lat_ID = Lattice.get(\"id\")\n", + " Write_Rect_Lattice(Lattice, py_file, Lat_ID)\n", + " for Cell in Geom_Root.findall(\"cell\"):\n", + " if Cell.get(\"fill\") == Lat_ID:\n", + " Cell_ID = int(Cell.get(\"id\"))\n", + "\n", + " py_file.write(\"c{} = mcdc.cell(\".format(Cell_ID))\n", + " Region_Fill(py_file=py_file, Cell=Cell)\n", + " py_file.write(f\"fill=Lattice{Lat_ID}\")\n", + "\n", + " if Cell.get(\"translation\") is not None:\n", + " tr = Cell.get(\"translation\").split()\n", + " py_file.write(f\", translation=[{tr[0]}, {tr[1]}, {tr[2]}]\")\n", + "\n", + " if Cell.get(\"rotation\") is not None:\n", + " rot = Cell.get(\"rotation\").split()[0]\n", + " py_file.write(f\", rotation=[{rot[0]}, {rot[1]}, {rot[2]}]\")\n", + "\n", + " py_file.write(\")\")\n", + "\n", + " if Cell.get(\"name\") != None:\n", + " py_file.write(f\" # Name: {Cell.get('name')}\\n\")\n", + " else:\n", + " py_file.write(f\"\\n\")\n", + " Lattice_Universe = Write_Universes(Geom_Root, py_file, Lat_ID)\n", + " Written_Universes += Lattice_Universe\n", + "\n", + " if py_file.name == \"Geometry_Only.py\":\n", + " py_file.close()\n", + " print(f\"Geometry MCDC File: ./{py_file.name}\")\n", + " return" + ] + }, + { + "cell_type": "code", + "execution_count": 7, + "metadata": {}, + "outputs": [], + "source": [ + "\n", + "def Settings_XML_Parser(XML_file=\"settings.xml\", py_file=None):\n", + " if py_file == None:\n", + " py_file = open(\"Settings_Only.py\", \"t+w\")\n", + " py_file.write(\"import mcdc\\nimport numpy as np\\n\\n\")\n", + " else:\n", + " py_file.write(\n", + " \"\\n\" + 30 * \"#\" + \"\\n#__________Settings__________\\n\" + 30 * \"#\" + \"\\n\\n\"\n", + " )\n", + "\n", + " Sett_Parse = et.parse(XML_file)\n", + "\n", + " Sett_Root = Sett_Parse.getroot()\n", + " if Sett_Root.tag == \"model\":\n", + " Sett_Root = Sett_Root.find(\"settings\")\n", + "\n", + " Settings_Dict = {}\n", + "\n", + " for Sett_key in [_.tag for _ in Sett_Root]:\n", + " if isinstance(Sett_key,str) == 0:\n", + " continue\n", + " if Sett_key in [\"particles\", \"batches\", \"inactive\", \"source\", \"output\"]:\n", + " continue # Ignores listed common settings\n", + " elif Sett_key in [\n", + " \"cutoff\",\n", + " \"keff_trigger\",\n", + " \"mesh\",\n", + " \"resonance_scattering\",\n", + " \"state_point\",\n", + " \"source_point\",\n", + " \"surf_source_read\",\n", + " \"surf_source_write\",\n", + " \"tabular_legendre\",\n", + " \"trigger\",\n", + " \"volume_calc\",\n", + " \"weight_windows\",\n", + " \"weight_window_generator\",\n", + " \"weight_window_checkpoints\",\n", + " ]: # Settings with Sub-Dictionaries\n", + " Sett_Val = {}\n", + " Parent = Sett_Root.find(Sett_key)\n", + " if Parent is not None:\n", + " for Sub in Parent:\n", + " Sub_key = Sub.tag\n", + " Sub_Val = Sub.text\n", + " Sett_Val[Sub_key] = Convert_Setting_Value(Sub_Val)\n", + " else: # All other uncommon settings with simple values\n", + " Element = Sett_Root.find(Sett_key)\n", + " if Element is not None and Element.text is not None:\n", + " Sett_Val = Element.text\n", + " Sett_Val = Convert_Setting_Value(Sett_Val)\n", + " else:\n", + " Sett_Val = None # Or another default value if needed \n", + " Settings_Dict[Sett_key] = Sett_Val\n", + "\n", + " if len(Settings_Dict) != 1:\n", + " py_file.write(\"# Original Conditions (Some Not Implemented)\\n\")\n", + " for (\n", + " key\n", + " ) in (\n", + " Settings_Dict.keys()\n", + " ): # Writes uncommon settings that are not implemented (Note: Weighting and Mesh not yet implemented)\n", + " if not key in [\"run_mode\", \"seed\"]:\n", + " py_file.write(f\"#\\t{key} = {Settings_Dict[key]}\\n\")\n", + "\n", + " py_file.write(\"# Simulation Parameters\\n\")\n", + " # Possible modes: eigenvalue, fixed source, plot, volume, particle reset (Last three not implemented)\n", + " if Settings_Dict[\"run_mode\"] == \"eigenvalue\":\n", + " N_Particles = int(Sett_Root.find(\"particles\").text)\n", + " N_Batches = int(Sett_Root.find(\"batches\").text)\n", + " N_Inactive = int(Sett_Root.find(\"inactive\").text)\n", + " N_Active = N_Batches - N_Inactive\n", + " # FIX: I manually set these to a particle count I wanted for the icsbep benchmarks. Change to actually copy openmc\n", + " #py_file.write(f\"mcdc.eigenmode(N_inactive={N_Inactive}, N_active={N_Active})\\n\")\n", + " py_file.write(f\"mcdc.eigenmode(N_inactive=20, N_active=180)\\n\")\n", + " #py_file.write(f\"mcdc.setting(N_particle={N_Particles}\")\n", + " py_file.write(f\"mcdc.setting(N_particle=10000\")\n", + " elif Settings_Dict[\"run_mode\"] == \"fixed source\":\n", + " N_Particles = int(Sett_Root.find(\"particles\").text)\n", + " N_Batches = int(Sett_Root.find(\"batches\").text)\n", + " py_file.write(f\"mcdc.setting(N_particle={N_Particles}, N_batch={N_Batches}\")\n", + " else:\n", + " py_file.write(f\"# Run mode: {Settings_Dict['run_mode']} Not Supported\")\n", + "\n", + " # Uses same seed int if recorded and closes settings function\n", + " if \"seed\" in Settings_Dict.keys():\n", + " py_file.write(f\", rng_seed={Settings_Dict['seed']})\\n\")\n", + " else:\n", + " py_file.write(\")\\n\")\n", + "\n", + " py_file.write(\"\\n# Source Parameters\\n\")\n", + " Source = Sett_Root.find(\"source\")\n", + " if Source == None:\n", + " py_file.write(\n", + " \"# Particle: neutron\\n# Space Type: Point\\n mcdc.source(point=[0.0,0.0,0.0], prob=1.0)\\n\"\n", + " )\n", + " else:\n", + " Particle = Source.get(\"particle\")\n", + " if Particle == None:\n", + " Particle = \"neutron\"\n", + " # P_Type = Source.get('type')\n", + " openmc_source_strength = Source.get(\"strength\")\n", + " if openmc_source_strength == None:\n", + " Strength = 1.0\n", + " else:\n", + " Strength = float(Source.get(\"strength\"))\n", + " Space = Source.find(\"space\")\n", + " #Space_Type = Space.get(\"type\")\n", + " if Space.find(\"type\") is not None:\n", + " Space_Type = Space.find(\"type\").text \n", + " else:\n", + " Space_Type = \"point\"\n", + " \n", + "\n", + "\n", + " py_file.write(f\"# Particle: {Particle}\\n\")\n", + " py_file.write(f\"# Space Type: {Space_Type}\")\n", + "\n", + " if Space_Type == \"point\":\n", + " if Space.find(\"type\") is not None:\n", + " Parameters = [\n", + " float(val) for val in Space.find(\"parameters\").text.split()\n", + " ]\n", + " else:\n", + " Parameters = [0.0, 0.0, 0.0]\n", + " py_file.write(\n", + " \"\\nmcdc.source(point=[{P[0]},{P[1]},{P[2]}], prob={S})\\n\".format(\n", + " P=Parameters, S=Strength\n", + " )\n", + " )\n", + " elif Space_Type == \"cartesian\":\n", + " Parameters = [0, 0, 0]\n", + " py_file.write(\" (Not Implemented, Replaced with Point)\\n\")\n", + " py_file.write(\n", + " \"mcdc.source(point=[{P[0]},{P[1]},{P[2]}], prob={S})\\n\".format(\n", + " P=Parameters, S=Strength\n", + " )\n", + " )\n", + " elif Space_Type == \"box\" or Space_Type == \"fission\":\n", + " Parameters = [\n", + " #float(val) for val in Space.find(\"parameters\").text.split(\" \")\n", + " float(val) for val in Space.find(\"parameters\").text.split() if val.strip()\n", + " ]\n", + " py_file.write(\n", + " \"\\nmcdc.source(x=[{P[0]},{P[3]}], y=[{P[1]},{P[4]}], z=[{P[2]},{P[5]}], prob={S})\\n\".format(\n", + " P=Parameters, S=Strength\n", + " )\n", + " )\n", + " elif Space_Type == \"spherical\":\n", + " Parameters = [float(val) for val in Space.get(\"origin\").split()]\n", + " Parameters += [\n", + " float(val) for val in Space.find(\"r\").get(\"parameters\").split()\n", + " ]\n", + " Parameters += [\n", + " float(val)\n", + " for val in Space.find(\"cos_theta\").get(\"parameters\").split()\n", + " ]\n", + " Parameters += [\n", + " float(val) for val in Space.find(\"phi\").get(\"parameters\").split()\n", + " ]\n", + " py_file.write(\" (Not Implemented, Replaced with Point)\\n\")\n", + " py_file.write(\n", + " \"mcdc.source(point=[{P[0]},{P[1]},{P[2]}], prob={S})\\n\".format(\n", + " P=Parameters, S=Strength\n", + " )\n", + " )\n", + " elif Space_Type == \"cylindrical\":\n", + " Parameters = [0, 0, 0]\n", + " py_file.write(\" (Not Implemented, Replaced with Point)\\n\")\n", + " py_file.write(\n", + " \"mcdc.source(point=[{P[0]},{P[1]},{P[2]}], prob={S})\\n\".format(\n", + " P=Parameters, S=Strength\n", + " )\n", + " )\n", + " elif Space_Type == \"mesh\":\n", + " Parameters = [0, 0, 0]\n", + " py_file.write(\" (Not Implemented, Replaced with Point)\\n\")\n", + " py_file.write(\n", + " \"nmcdc.source(point=[{P[0]},{P[1]},{P[2]}], prob={S})\\n\".format(\n", + " P=Parameters, S=Strength\n", + " )\n", + " )\n", + "\n", + " if py_file.name == \"Settings_Only.py\":\n", + " py_file.close()\n", + " print(f\"Settings MCDC File: ./{py_file.name}\")\n", + " return\n" + ] + }, + { + "cell_type": "code", + "execution_count": 8, + "metadata": {}, + "outputs": [], + "source": [ + "\n", + "# Ultimate function for running all parsers\n", + "def OpenMC_to_MCDC(\n", + " output_name=\"input.py\",\n", + " materials_xml=\"materials.xml\",\n", + " geometry_xml=\"geometry.xml\",\n", + " settings_xml=\"settings.xml\",\n", + " model_xml=None,\n", + "):\n", + " \"\"\"Constructs python file (output_name) into folder location. Defines nuclear system input deck compatable with MC/DC\n", + " terminology from OpenMC input deck files (materials.xml, geometry.xml, settings.xml, etc.) within folder location.\n", + "\n", + " .. version:: 0.1.4\n", + "\n", + " Parameters\n", + " ----------\n", + " output_name : str, optional\n", + " Name of new python file, must end in '.py'\n", + " materials_xml : str, optional\n", + " Name of materials file, must end in '.xml'\n", + " geometry_xml : str, optional\n", + " Name of geometry file, must end in '.xml'\n", + " settings_xml : str, optional\n", + " Name of settings file, must end in '.xml'\n", + " model_xml : str, optional\n", + " Name of model file, must end in '.xml',\n", + " overrides individual xml files\n", + "\n", + " Returns\n", + " -------\n", + " None\\n\n", + " Prints created file link\n", + " \"\"\"\n", + "\n", + " # Check input parameters\n", + " assert output_name[-3:] == \".py\", \"New file must be a python file\"\n", + " assert materials_xml[-4:] == \".xml\", \"Improper Geometry input file name\"\n", + " assert geometry_xml[-4:] == \".xml\", \"Improper Materials input file name\"\n", + " assert settings_xml[-4:] == \".xml\", \"Improper Settings input file name\"\n", + " if model_xml is not None and os.path.isfile(model_xml):\n", + " assert model_xml[-4:] == \".xml\", \"Improper Model input file name\"\n", + " materials_xml = model_xml\n", + " geometry_xml = model_xml\n", + " settings_xml = model_xml\n", + "\n", + " # Create file\n", + " MCDC_Code = open(output_name, \"t+w\")\n", + "\n", + " # Imports\n", + " MCDC_Code.write(\"import mcdc\\nimport numpy as np\\n\\n\")\n", + "\n", + " # Parse materials, geometry, and settings\n", + " Materials_XML_Parser(XML_file=materials_xml, py_file=MCDC_Code)\n", + " Geometry_XML_Parser(XML_file=geometry_xml, py_file=MCDC_Code)\n", + " Settings_XML_Parser(XML_file=settings_xml, py_file=MCDC_Code)\n", + "\n", + " MCDC_Code.write(\"\\nmcdc.run()\\n\\n\")\n", + "\n", + " # Close file and report\n", + " MCDC_Code.close()\n", + " print(\"MCDC Input File Constructed: .\\{}\".format(output_name))\n" + ] + }, + { + "cell_type": "code", + "execution_count": 9, + "metadata": {}, + "outputs": [], + "source": [ + "\n", + "\n", + "def find_and_translate(base_dir):\n", + " \"\"\"\n", + " Recursively find all openmc directories containing the required XML files, \n", + " create mcdc directory next to them, and run the translator.\n", + " \"\"\"\n", + " required_files = {\"materials.xml\", \"geometry.xml\", \"settings.xml\"}\n", + " num_failed = 0\n", + " num_built = 0\n", + " failed_list = []\n", + " for root, dirs, files in os.walk(base_dir):\n", + " #if root != \"/usr/workspace/northroj/dane_mcdc_openmc/icsbep/openmc/heu-met-fast-002/openmc/case-5\":\n", + " # continue\n", + " try:\n", + " # Check for case 1: XMLs directly in openmc folder\n", + " if os.path.basename(root) == \"openmc\" and required_files.issubset(set(files)):\n", + " openmc_dir = root\n", + " parent_dir = os.path.dirname(openmc_dir)\n", + " problem_name = os.path.basename(parent_dir)\n", + " mcdc_dir = os.path.join(parent_dir, \"mcdc\")\n", + " \n", + " # Create mcdc directory if it doesn't exist\n", + " if not os.path.exists(mcdc_dir):\n", + " os.makedirs(mcdc_dir)\n", + "\n", + " # Name the output file using the problem name\n", + " output_name = os.path.join(mcdc_dir, f\"{problem_name}.py\")\n", + " materials_xml = os.path.join(openmc_dir, \"materials.xml\")\n", + " geometry_xml = os.path.join(openmc_dir, \"geometry.xml\")\n", + " settings_xml = os.path.join(openmc_dir, \"settings.xml\")\n", + " \n", + " # Run the translator\n", + " print(f\"Translating OpenMC inputs in {openmc_dir} to {output_name}...\")\n", + " OpenMC_to_MCDC(\n", + " output_name=output_name,\n", + " materials_xml=materials_xml,\n", + " geometry_xml=geometry_xml,\n", + " settings_xml=settings_xml,\n", + " )\n", + " print(f\"Translation complete: {output_name}\")\n", + " num_built += 1\n", + "\n", + " # Check for case 2: XMLs in subfolders of openmc (e.g., openmc//)\n", + " elif os.path.basename(os.path.dirname(root)) == \"openmc\" and required_files.issubset(set(files)):\n", + " case_dir = root\n", + " openmc_dir = os.path.dirname(case_dir)\n", + " parent_dir = os.path.dirname(openmc_dir)\n", + " problem_name = os.path.basename(parent_dir)\n", + " case_name = os.path.basename(case_dir)\n", + " mcdc_dir = os.path.join(parent_dir, \"mcdc\")\n", + " \n", + " # Create mcdc directory if it doesn't exist\n", + " if not os.path.exists(mcdc_dir):\n", + " os.makedirs(mcdc_dir)\n", + "\n", + " # Name the output file using problem name and case name\n", + " output_name = os.path.join(mcdc_dir, f\"{problem_name}_{case_name}.py\")\n", + " materials_xml = os.path.join(case_dir, \"materials.xml\")\n", + " geometry_xml = os.path.join(case_dir, \"geometry.xml\")\n", + " settings_xml = os.path.join(case_dir, \"settings.xml\")\n", + " \n", + " # Run the translator\n", + " print(f\"Translating OpenMC inputs in {case_dir} to {output_name}...\")\n", + " OpenMC_to_MCDC(\n", + " output_name=output_name,\n", + " materials_xml=materials_xml,\n", + " geometry_xml=geometry_xml,\n", + " settings_xml=settings_xml,\n", + " )\n", + " print(f\"Translation complete: {output_name}\")\n", + " num_built += 1\n", + "\n", + " except Exception as e:\n", + " print(f\"Exeption: {e}\")\n", + " num_failed += 1\n", + " failed_list.append(openmc_dir)\n", + " \n", + " print(num_failed, \"failures\")\n", + " print(num_built, \"built\")\n", + " print(failed_list)" + ] + }, + { + "cell_type": "code", + "execution_count": 1, + "metadata": {}, + "outputs": [ + { + "ename": "NameError", + "evalue": "name 'find_and_translate' is not defined", + "output_type": "error", + "traceback": [ + "\u001b[0;31m---------------------------------------------------------------------------\u001b[0m", + "\u001b[0;31mNameError\u001b[0m Traceback (most recent call last)", + "Cell \u001b[0;32mIn[1], line 3\u001b[0m\n\u001b[1;32m 1\u001b[0m \u001b[38;5;66;03m# Specify the base directory to start the search\u001b[39;00m\n\u001b[1;32m 2\u001b[0m base_dir \u001b[38;5;241m=\u001b[39m \u001b[38;5;124m\"\u001b[39m\u001b[38;5;124m/MCDC-verification/icsbep/openmc\u001b[39m\u001b[38;5;124m\"\u001b[39m\n\u001b[0;32m----> 3\u001b[0m \u001b[43mfind_and_translate\u001b[49m(base_dir)\n", + "\u001b[0;31mNameError\u001b[0m: name 'find_and_translate' is not defined" + ] + } + ], + "source": [ + "# Specify the base directory to start the search\n", + "base_dir = \"/MCDC-verification/icsbep/openmc\"\n", + "find_and_translate(base_dir)" + ] + } + ], + "metadata": { + "kernelspec": { + "display_name": "openmc_dane_env", + "language": "python", + "name": "python3" + }, + "language_info": { + "codemirror_mode": { + "name": "ipython", + "version": 3 + }, + "file_extension": ".py", + "mimetype": "text/x-python", + "name": "python", + "nbconvert_exporter": "python", + "pygments_lexer": "ipython3", + "version": "3.11.11" + } + }, + "nbformat": 4, + "nbformat_minor": 2 +} diff --git a/icsbep/openmc/collect_results.py b/icsbep/openmc/collect_results.py new file mode 100644 index 0000000..595dc8d --- /dev/null +++ b/icsbep/openmc/collect_results.py @@ -0,0 +1,146 @@ +import os +import h5py +import pandas as pd +import re +import numpy as np +import matplotlib.pyplot as plt + +def extract_mcdc_results(mcdc_dir): + results = {} + for file in os.listdir(mcdc_dir): + if file.endswith(".h5"): + file_path = os.path.join(mcdc_dir, file) + print("Extracting MC/DC results from:", file_path) + try: + with h5py.File(file_path, 'r') as f: + k_mean = np.array(f["k_mean"]) + k_sdev = np.array(f["k_sdev"]) + print(k_mean) + if k_mean is not None and k_sdev is not None: + problem_name = file.replace(".h5", "") + results[problem_name] = {"mcdc_k_mean": k_mean, "mcdc_k_sdev": k_sdev} + except Exception as e: + print(f"Error reading {file_path}: {e}") + return results + +def extract_openmc_results(openmc_dir): + results = {} + parent_dir = os.path.basename(os.path.dirname(openmc_dir)) + case_dirs = [os.path.join(openmc_dir, d) for d in os.listdir(openmc_dir) if d.startswith("case-") and os.path.isdir(os.path.join(openmc_dir, d))] + + if not case_dirs: + case_dirs = [openmc_dir] # If no case-# subdirectories, use openmc_dir itself + + for case_dir in case_dirs: + stdout_file = os.path.join(case_dir, "openmc.stdout") + if os.path.exists(stdout_file): + print("Extracting openmc results from:", case_dir) + try: + with open(stdout_file, 'r') as f: + for line in f: + match = re.search(r'Combined k-effective\s+=\s+([\d\.]+)\s+\+/-\s+([\d\.]+)', line) + if match: + k_mean = float(match.group(1)) + k_sdev = float(match.group(2)) + case_name = os.path.basename(case_dir) if "case-" in case_dir else "" + problem_name = f"{parent_dir}_{case_name}" if case_name else parent_dir + results[problem_name] = {"openmc_k_mean": k_mean, "openmc_k_sdev": k_sdev} + break # Stop after finding the first match + except Exception as e: + print(f"Error reading {stdout_file}: {e}") + return results + +def collect_results1(root_dir): + dataset = {} + + for dirpath, dirnames, _ in os.walk(root_dir): + if "mcdc" in dirnames: + mcdc_results = extract_mcdc_results(os.path.join(dirpath, "mcdc")) + dataset.update(mcdc_results) + if "openmc" in dirnames: + openmc_results = extract_openmc_results(os.path.join(dirpath, "openmc")) + dataset.update(openmc_results) + df = pd.DataFrame.from_dict(dataset, orient='index').reset_index().rename(columns={'index': 'problem_name'}) + df.to_csv("results_summary.csv", index=False) + print("Results collected and saved to results_summary.csv") + +def collect_results(root_dir): + dataset = {} + + for dirpath, dirnames, _ in os.walk(root_dir): + if "mcdc" in dirnames: + mcdc_results = extract_mcdc_results(os.path.join(dirpath, "mcdc")) + for problem_name, values in mcdc_results.items(): + if problem_name not in dataset: + dataset[problem_name] = {} + dataset[problem_name].update(values) + + if "openmc" in dirnames: + openmc_results = extract_openmc_results(os.path.join(dirpath, "openmc")) + for problem_name, values in openmc_results.items(): + if problem_name not in dataset: + dataset[problem_name] = {} + dataset[problem_name].update(values) + + # Convert to DataFrame and ensure all columns exist + df = pd.DataFrame.from_dict(dataset, orient='index').reset_index().rename(columns={'index': 'problem_name'}) + + # Ensure all columns exist, filling missing values with NaN + expected_columns = ["problem_name", "openmc_k_mean", "openmc_k_sdev", "mcdc_k_mean", "mcdc_k_sdev"] + df = df.reindex(columns=expected_columns) + + # Save to CSV + df.to_csv("results_summary.csv", index=False) + print("Results collected and saved to results_summary.csv") + +#root_directory = os.getcwd() # Start search from current directory +#collect_results(root_directory) + + + + +### plotting +plotting_toggle = 1 + +def plot_icsbep_comparison(df, title): + + # Set up the plot + plt.figure(figsize=(12, 6)) + x_labels = df["problem_name"] + x = np.arange(len(x_labels)) # Create x positions for labels + + # Plot OpenMC and MCDC k_mean values + plt.scatter(x, df["openmc_k_mean"], marker='o', label="OpenMC" , color='b') + plt.errorbar(x, df["openmc_k_mean"], yerr=df["openmc_k_sdev"], fmt='o', color='b', capsize=3) + plt.scatter(x, df["mcdc_k_mean"], marker='s', label="MC/DC", color='r') + plt.errorbar(x, df["mcdc_k_mean"], yerr=df["mcdc_k_sdev"], fmt='o', color='r', capsize=3) + + # Format the x-axis for better readability + plt.xticks(x, x_labels, rotation=45, ha="right", fontsize=8) # Rotate labels + #plt.xlabel("Problem Name") + plt.ylabel("keff") + plt.title(title) + plt.legend() + plt.grid(axis="y", linestyle="--", alpha=0.7) + +# Load the CSV file +df = pd.read_csv("results_summary.csv") +df = df[:118] + +df_heu_met_fast = df[:25] +df_heu_sol_therm = df[25:44] +df_misc = pd.concat([df[44:48], df[56:57], df[117:118]]) +df_leu_sol_therm = df[48:56] +df_pu_met_fast = df[57:64] +df_pu_sol_therm = df[64:108] +df_u233_met_fast = df[108:117] + +if plotting_toggle == 1: + plot_icsbep_comparison(df_heu_met_fast, "ICSBEP: HEU-MET-FAST") + plot_icsbep_comparison(df_heu_sol_therm, "ICSBEP: HEU-SOL-THERM") + plot_icsbep_comparison(df_misc, "ICSBEP: Miscellaneous") + plot_icsbep_comparison(df_leu_sol_therm, "ICSBEP: LEU-SOL-THERM") + plot_icsbep_comparison(df_pu_met_fast, "ICSBEP: PU-MET-FAST") + plot_icsbep_comparison(df_pu_sol_therm, "ICSBEP: PU-SOL-THERM") + plot_icsbep_comparison(df_u233_met_fast, "ICSBEP: U233-MET-FAST") + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-1.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-1.py new file mode 100644 index 0000000..9ae95a1 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-1.py @@ -0,0 +1,218 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +# Material Name: HEU, Can A +# Depletable +m15 = mcdc.material(nuclides=[ + ['U235',0.02303], + ['U238',0.0013124], + ['H1',0.07027905303540001], + ['H2',1.09469646e-05], + ['O16',0.00060008248251], + ['O17',2.2751749e-07], + ['C0',9.6792e-05], + ['N14',0.00026208644785000006], + ['N15',9.6355215e-07], + ['Fe54',5.25202475e-06], + ['Fe56',8.24455567e-05], + ['Fe57',1.9040274499999997e-06], + ['Fe58',2.533911e-07], + ['Au197',0.00032844]]) +# Material Name: HEU, Can B +# Depletable +m16 = mcdc.material(nuclides=[ + ['U235',0.022951], + ['U238',0.0013058], + ['H1',0.0732285936024], + ['H2',1.14063976e-05], + ['O16',0.0004934129256], + ['O17',1.870744e-07], + ['C0',0.00012804], + ['N14',0.00022934681403], + ['N15',8.4318597e-07], + ['Fe54',3.9574157e-06], + ['Fe56',6.212296324000001e-05], + ['Fe57',1.4346901400000002e-06], + ['Fe58',1.9093092e-07], + ['Au197',0.0003014]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=7.42, bc='interface') +s4 = mcdc.surface('plane-z', z=7.5788, bc='interface') +s5 = mcdc.surface('plane-z', z=7.5998, bc='interface') +s6 = mcdc.surface('plane-z', z=9.6089, bc='interface') +s7 = mcdc.surface('plane-z', z=9.6299, bc='interface') +s8 = mcdc.surface('plane-z', z=9.6553, bc='interface') +s9 = mcdc.surface('plane-z', z=12.6274, bc='interface') +s10 = mcdc.surface('plane-z', z=12.6528, bc='interface') +s11 = mcdc.surface('plane-z', z=14.8959, bc='interface') +s12 = mcdc.surface('plane-z', z=14.9213, bc='interface') +s13 = mcdc.surface('plane-z', z=17.9219, bc='interface') +s14 = mcdc.surface('plane-z', z=17.9473, bc='interface') +s15 = mcdc.surface('plane-z', z=17.9683, bc='interface') +s16 = mcdc.surface('plane-z', z=19.9808, bc='interface') +s17 = mcdc.surface('plane-z', z=20.0018, bc='interface') +s18 = mcdc.surface('plane-z', z=20.1606, bc='interface') +s19 = mcdc.surface('plane-z', z=27.5806, bc='interface') +s20 = mcdc.surface('plane-z', z=30.0685, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s22 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s23 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.1409, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s28, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s24, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s23, fill=m3) +c4 = mcdc.cell(+s3 & -s4 & +s23 & -s24, fill=mvoid) +c5 = mcdc.cell(+s4 & -s5 & -s24, fill=m3) +c6 = mcdc.cell(+s5 & -s6 & -s23, fill=m15) +c7 = mcdc.cell(+s5 & -s6 & +s23 & -s24, fill=m3) +c8 = mcdc.cell(+s6 & -s7 & -s24, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & -s24, fill=m3) +c10 = mcdc.cell(+s8 & -s9 & -s23, fill=m12) +c11 = mcdc.cell(+s8 & -s9 & +s23 & -s24, fill=m3) +c12 = mcdc.cell(+s9 & -s10 & -s24, fill=m3) +c13 = mcdc.cell(+s10 & -s11 & -s21, fill=mvoid) +c14 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m1) +c15 = mcdc.cell(+s10 & -s11 & +s22 & -s24, fill=mvoid) +c16 = mcdc.cell(+s11 & -s12 & -s24, fill=m3) +c17 = mcdc.cell(+s12 & -s13 & -s23, fill=m11) +c18 = mcdc.cell(+s12 & -s13 & +s23 & -s24, fill=m3) +c19 = mcdc.cell(+s13 & -s14 & -s24, fill=m3) +c20 = mcdc.cell(+s14 & -s15 & -s24, fill=m3) +c21 = mcdc.cell(+s15 & -s16 & -s23, fill=m16) +c22 = mcdc.cell(+s15 & -s16 & +s23 & -s24, fill=m3) +c23 = mcdc.cell(+s16 & -s17 & -s24, fill=m3) +c24 = mcdc.cell(+s17 & -s18 & -s23, fill=m3) +c25 = mcdc.cell(+s17 & -s18 & +s23 & -s24, fill=mvoid) +c26 = mcdc.cell(+s18 & -s19 & -s24, fill=m2) +c27 = mcdc.cell(+s19 & -s20 & -s24, fill=mvoid) +c28 = mcdc.cell(+s2 & -s20 & +s24 & -s25, fill=mvoid) +c29 = mcdc.cell(+s2 & -s20 & +s25 & -s26, fill=m4) +c30 = mcdc.cell(+s2 & -s20 & +s26 & -s27, fill=mvoid) +c31 = mcdc.cell(+s2 & -s20 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-2.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-2.py new file mode 100644 index 0000000..1399909 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-2.py @@ -0,0 +1,231 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: Be +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +# Material Name: HEU, Can A +# Depletable +m15 = mcdc.material(nuclides=[ + ['U235',0.02303], + ['U238',0.0013124], + ['H1',0.07027905303540001], + ['H2',1.09469646e-05], + ['O16',0.00060008248251], + ['O17',2.2751749e-07], + ['C0',9.6792e-05], + ['N14',0.00026208644785000006], + ['N15',9.6355215e-07], + ['Fe54',5.25202475e-06], + ['Fe56',8.24455567e-05], + ['Fe57',1.9040274499999997e-06], + ['Fe58',2.533911e-07], + ['Au197',0.00032844]]) +# Material Name: HEU, Can B +# Depletable +m16 = mcdc.material(nuclides=[ + ['U235',0.022951], + ['U238',0.0013058], + ['H1',0.0732285936024], + ['H2',1.14063976e-05], + ['O16',0.0004934129256], + ['O17',1.870744e-07], + ['C0',0.00012804], + ['N14',0.00022934681403], + ['N15',8.4318597e-07], + ['Fe54',3.9574157e-06], + ['Fe56',6.212296324000001e-05], + ['Fe57',1.4346901400000002e-06], + ['Fe58',1.9093092e-07], + ['Au197',0.0003014]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=5.08, bc='interface') +s4 = mcdc.surface('plane-z', z=7.42, bc='interface') +s5 = mcdc.surface('plane-z', z=7.441, bc='interface') +s6 = mcdc.surface('plane-z', z=9.4501, bc='interface') +s7 = mcdc.surface('plane-z', z=9.4711, bc='interface') +s8 = mcdc.surface('plane-z', z=9.6299, bc='interface') +s9 = mcdc.surface('plane-z', z=9.6553, bc='interface') +s10 = mcdc.surface('plane-z', z=12.6274, bc='interface') +s11 = mcdc.surface('plane-z', z=12.6528, bc='interface') +s12 = mcdc.surface('plane-z', z=16.1867, bc='interface') +s13 = mcdc.surface('plane-z', z=16.2121, bc='interface') +s14 = mcdc.surface('plane-z', z=19.2127, bc='interface') +s15 = mcdc.surface('plane-z', z=19.2381, bc='interface') +s16 = mcdc.surface('plane-z', z=19.2591, bc='interface') +s17 = mcdc.surface('plane-z', z=21.2716, bc='interface') +s18 = mcdc.surface('plane-z', z=21.2926, bc='interface') +s19 = mcdc.surface('plane-z', z=21.4514, bc='interface') +s20 = mcdc.surface('plane-z', z=23.7914, bc='interface') +s21 = mcdc.surface('plane-z', z=24.9885, bc='interface') +s22 = mcdc.surface('plane-z', z=28.8714, bc='interface') +s23 = mcdc.surface('plane-z', z=30.0685, bc='vacuum') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s29 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=10.0432, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.1409, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s32, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s27, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s27, fill=m5) +c4 = mcdc.cell(+s4 & -s5 & -s27, fill=m3) +c5 = mcdc.cell(+s5 & -s6 & -s26, fill=m15) +c6 = mcdc.cell(+s5 & -s6 & +s26 & -s27, fill=m3) +c7 = mcdc.cell(+s6 & -s7 & -s27, fill=m3) +c8 = mcdc.cell(+s7 & -s8 & -s26, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & +s26 & -s27, fill=mvoid) +c10 = mcdc.cell(+s8 & -s9 & -s27, fill=m3) +c11 = mcdc.cell(+s9 & -s10 & -s26, fill=m12) +c12 = mcdc.cell(+s9 & -s10 & +s26 & -s27, fill=m3) +c13 = mcdc.cell(+s10 & -s11 & -s27, fill=m3) +c14 = mcdc.cell(+s11 & -s12 & -s24, fill=mvoid) +c15 = mcdc.cell(+s11 & -s12 & +s24 & -s25, fill=m1) +c16 = mcdc.cell(+s11 & -s12 & +s25 & -s27, fill=mvoid) +c17 = mcdc.cell(+s12 & -s13 & -s27, fill=m3) +c18 = mcdc.cell(+s13 & -s14 & -s26, fill=m11) +c19 = mcdc.cell(+s13 & -s14 & +s26 & -s27, fill=m3) +c20 = mcdc.cell(+s14 & -s15 & -s27, fill=m3) +c21 = mcdc.cell(+s15 & -s16 & -s27, fill=m3) +c22 = mcdc.cell(+s16 & -s17 & -s26, fill=m16) +c23 = mcdc.cell(+s16 & -s17 & +s26 & -s27, fill=m3) +c24 = mcdc.cell(+s17 & -s18 & -s27, fill=m3) +c25 = mcdc.cell(+s18 & -s19 & -s26, fill=m3) +c26 = mcdc.cell(+s18 & -s19 & +s26 & -s27, fill=mvoid) +c27 = mcdc.cell(+s19 & -s20 & -s27, fill=m5) +c28 = mcdc.cell(+s20 & -s22 & -s27, fill=m2) +c29 = mcdc.cell(+s22 & -s23 & -s27, fill=mvoid) +c30 = mcdc.cell(+s3 & -s21 & +s30 & -s31, fill=m5) +c31 = mcdc.cell(+s2 & -s23 & +s27 & -s28, fill=mvoid) +c32 = mcdc.cell(+s2 & -s23 & +s28 & -s29, fill=m4) +c33 = mcdc.cell(+s2 & -s23 & +s29 & -s30, fill=mvoid) +c34 = mcdc.cell(+s2 & -s3 & +s30 & -s31, fill=m2) +c35 = mcdc.cell(+s21 & -s23 & +s30 & -s31, fill=m2) +c36 = mcdc.cell(+s2 & -s23 & +s31 & -s32, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-3.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-3.py new file mode 100644 index 0000000..a344f9d --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-3.py @@ -0,0 +1,231 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: Be +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +# Material Name: HEU, Can A +# Depletable +m15 = mcdc.material(nuclides=[ + ['U235',0.02303], + ['U238',0.0013124], + ['H1',0.07027905303540001], + ['H2',1.09469646e-05], + ['O16',0.00060008248251], + ['O17',2.2751749e-07], + ['C0',9.6792e-05], + ['N14',0.00026208644785000006], + ['N15',9.6355215e-07], + ['Fe54',5.25202475e-06], + ['Fe56',8.24455567e-05], + ['Fe57',1.9040274499999997e-06], + ['Fe58',2.533911e-07], + ['Au197',0.00032844]]) +# Material Name: HEU, Can B +# Depletable +m16 = mcdc.material(nuclides=[ + ['U235',0.022951], + ['U238',0.0013058], + ['H1',0.0732285936024], + ['H2',1.14063976e-05], + ['O16',0.0004934129256], + ['O17',1.870744e-07], + ['C0',0.00012804], + ['N14',0.00022934681403], + ['N15',8.4318597e-07], + ['Fe54',3.9574157e-06], + ['Fe56',6.212296324000001e-05], + ['Fe57',1.4346901400000002e-06], + ['Fe58',1.9093092e-07], + ['Au197',0.0003014]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=5.08, bc='interface') +s4 = mcdc.surface('plane-z', z=7.42, bc='interface') +s5 = mcdc.surface('plane-z', z=7.5788, bc='interface') +s6 = mcdc.surface('plane-z', z=7.5998, bc='interface') +s7 = mcdc.surface('plane-z', z=9.6089, bc='interface') +s8 = mcdc.surface('plane-z', z=9.6299, bc='interface') +s9 = mcdc.surface('plane-z', z=9.6553, bc='interface') +s10 = mcdc.surface('plane-z', z=12.6274, bc='interface') +s11 = mcdc.surface('plane-z', z=12.6528, bc='interface') +s12 = mcdc.surface('plane-z', z=16.3582, bc='interface') +s13 = mcdc.surface('plane-z', z=16.3836, bc='interface') +s14 = mcdc.surface('plane-z', z=19.3842, bc='interface') +s15 = mcdc.surface('plane-z', z=19.4096, bc='interface') +s16 = mcdc.surface('plane-z', z=19.4306, bc='interface') +s17 = mcdc.surface('plane-z', z=21.4431, bc='interface') +s18 = mcdc.surface('plane-z', z=21.4641, bc='interface') +s19 = mcdc.surface('plane-z', z=21.6229, bc='interface') +s20 = mcdc.surface('plane-z', z=23.9629, bc='interface') +s21 = mcdc.surface('plane-z', z=24.9885, bc='interface') +s22 = mcdc.surface('plane-z', z=29.0429, bc='interface') +s23 = mcdc.surface('plane-z', z=30.0685, bc='vacuum') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s29 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=10.0432, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.1409, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s32, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s27, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s27, fill=m5) +c4 = mcdc.cell(+s4 & -s5 & -s26, fill=m3) +c5 = mcdc.cell(+s4 & -s5 & +s26 & -s27, fill=mvoid) +c6 = mcdc.cell(+s5 & -s6 & -s27, fill=m3) +c7 = mcdc.cell(+s6 & -s7 & -s26, fill=m15) +c8 = mcdc.cell(+s6 & -s7 & +s26 & -s27, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & -s27, fill=m3) +c10 = mcdc.cell(+s8 & -s9 & -s27, fill=m3) +c11 = mcdc.cell(+s9 & -s10 & -s26, fill=m12) +c12 = mcdc.cell(+s9 & -s10 & +s26 & -s27, fill=m3) +c13 = mcdc.cell(+s10 & -s11 & -s27, fill=m3) +c14 = mcdc.cell(+s11 & -s12 & -s24, fill=mvoid) +c15 = mcdc.cell(+s11 & -s12 & +s24 & -s25, fill=m1) +c16 = mcdc.cell(+s11 & -s12 & +s25 & -s27, fill=mvoid) +c17 = mcdc.cell(+s12 & -s13 & -s27, fill=m3) +c18 = mcdc.cell(+s13 & -s14 & -s26, fill=m11) +c19 = mcdc.cell(+s13 & -s14 & +s26 & -s27, fill=m3) +c20 = mcdc.cell(+s14 & -s15 & -s27, fill=m3) +c21 = mcdc.cell(+s15 & -s16 & -s27, fill=m3) +c22 = mcdc.cell(+s16 & -s17 & -s26, fill=m16) +c23 = mcdc.cell(+s16 & -s17 & +s26 & -s27, fill=m3) +c24 = mcdc.cell(+s17 & -s18 & -s27, fill=m3) +c25 = mcdc.cell(+s18 & -s19 & -s26, fill=m3) +c26 = mcdc.cell(+s18 & -s19 & +s26 & -s27, fill=mvoid) +c27 = mcdc.cell(+s19 & -s20 & -s27, fill=m5) +c28 = mcdc.cell(+s20 & -s22 & -s27, fill=m2) +c29 = mcdc.cell(+s22 & -s23 & -s27, fill=mvoid) +c30 = mcdc.cell(+s3 & -s21 & +s30 & -s31, fill=m5) +c31 = mcdc.cell(+s2 & -s23 & +s27 & -s28, fill=mvoid) +c32 = mcdc.cell(+s2 & -s23 & +s28 & -s29, fill=m4) +c33 = mcdc.cell(+s2 & -s23 & +s29 & -s30, fill=mvoid) +c34 = mcdc.cell(+s2 & -s3 & +s30 & -s31, fill=m2) +c35 = mcdc.cell(+s21 & -s23 & +s30 & -s31, fill=m2) +c36 = mcdc.cell(+s2 & -s23 & +s31 & -s32, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-4.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-4.py new file mode 100644 index 0000000..201b264 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-4.py @@ -0,0 +1,231 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: Be +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +# Material Name: HEU, Can A +# Depletable +m15 = mcdc.material(nuclides=[ + ['U235',0.02303], + ['U238',0.0013124], + ['H1',0.07027905303540001], + ['H2',1.09469646e-05], + ['O16',0.00060008248251], + ['O17',2.2751749e-07], + ['C0',9.6792e-05], + ['N14',0.00026208644785000006], + ['N15',9.6355215e-07], + ['Fe54',5.25202475e-06], + ['Fe56',8.24455567e-05], + ['Fe57',1.9040274499999997e-06], + ['Fe58',2.533911e-07], + ['Au197',0.00032844]]) +# Material Name: HEU, Can B +# Depletable +m16 = mcdc.material(nuclides=[ + ['U235',0.022951], + ['U238',0.0013058], + ['H1',0.0732285936024], + ['H2',1.14063976e-05], + ['O16',0.0004934129256], + ['O17',1.870744e-07], + ['C0',0.00012804], + ['N14',0.00022934681403], + ['N15',8.4318597e-07], + ['Fe54',3.9574157e-06], + ['Fe56',6.212296324000001e-05], + ['Fe57',1.4346901400000002e-06], + ['Fe58',1.9093092e-07], + ['Au197',0.0003014]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=5.08, bc='interface') +s4 = mcdc.surface('plane-z', z=7.42, bc='interface') +s5 = mcdc.surface('plane-z', z=7.5788, bc='interface') +s6 = mcdc.surface('plane-z', z=7.5998, bc='interface') +s7 = mcdc.surface('plane-z', z=9.6089, bc='interface') +s8 = mcdc.surface('plane-z', z=9.6299, bc='interface') +s9 = mcdc.surface('plane-z', z=9.6553, bc='interface') +s10 = mcdc.surface('plane-z', z=12.6274, bc='interface') +s11 = mcdc.surface('plane-z', z=12.6528, bc='interface') +s12 = mcdc.surface('plane-z', z=14.0259, bc='interface') +s13 = mcdc.surface('plane-z', z=14.0513, bc='interface') +s14 = mcdc.surface('plane-z', z=17.0519, bc='interface') +s15 = mcdc.surface('plane-z', z=17.0773, bc='interface') +s16 = mcdc.surface('plane-z', z=17.0983, bc='interface') +s17 = mcdc.surface('plane-z', z=19.1108, bc='interface') +s18 = mcdc.surface('plane-z', z=19.1318, bc='interface') +s19 = mcdc.surface('plane-z', z=19.2906, bc='interface') +s20 = mcdc.surface('plane-z', z=21.6306, bc='interface') +s21 = mcdc.surface('plane-z', z=24.9885, bc='interface') +s22 = mcdc.surface('plane-z', z=26.7106, bc='interface') +s23 = mcdc.surface('plane-z', z=30.0685, bc='vacuum') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s29 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=10.0609, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.1409, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s32, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s27, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s27, fill=m4) +c4 = mcdc.cell(+s4 & -s5 & -s26, fill=m3) +c5 = mcdc.cell(+s4 & -s5 & +s26 & -s27, fill=mvoid) +c6 = mcdc.cell(+s5 & -s6 & -s27, fill=m3) +c7 = mcdc.cell(+s6 & -s7 & -s26, fill=m15) +c8 = mcdc.cell(+s6 & -s7 & +s26 & -s27, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & -s27, fill=m3) +c10 = mcdc.cell(+s8 & -s9 & -s27, fill=m3) +c11 = mcdc.cell(+s9 & -s10 & -s26, fill=m12) +c12 = mcdc.cell(+s9 & -s10 & +s26 & -s27, fill=m3) +c13 = mcdc.cell(+s10 & -s11 & -s27, fill=m3) +c14 = mcdc.cell(+s11 & -s12 & -s24, fill=mvoid) +c15 = mcdc.cell(+s11 & -s12 & +s24 & -s25, fill=m1) +c16 = mcdc.cell(+s11 & -s12 & +s25 & -s27, fill=mvoid) +c17 = mcdc.cell(+s12 & -s13 & -s27, fill=m3) +c18 = mcdc.cell(+s13 & -s14 & -s26, fill=m11) +c19 = mcdc.cell(+s13 & -s14 & +s26 & -s27, fill=m3) +c20 = mcdc.cell(+s14 & -s15 & -s27, fill=m3) +c21 = mcdc.cell(+s15 & -s16 & -s27, fill=m3) +c22 = mcdc.cell(+s16 & -s17 & -s26, fill=m16) +c23 = mcdc.cell(+s16 & -s17 & +s26 & -s27, fill=m3) +c24 = mcdc.cell(+s17 & -s18 & -s27, fill=m3) +c25 = mcdc.cell(+s18 & -s19 & -s26, fill=m3) +c26 = mcdc.cell(+s18 & -s19 & +s26 & -s27, fill=mvoid) +c27 = mcdc.cell(+s19 & -s20 & -s27, fill=m4) +c28 = mcdc.cell(+s20 & -s22 & -s27, fill=m2) +c29 = mcdc.cell(+s22 & -s23 & -s27, fill=mvoid) +c30 = mcdc.cell(+s3 & -s21 & +s30 & -s31, fill=m4) +c31 = mcdc.cell(+s2 & -s23 & +s27 & -s28, fill=mvoid) +c32 = mcdc.cell(+s2 & -s23 & +s28 & -s29, fill=m4) +c33 = mcdc.cell(+s2 & -s23 & +s29 & -s30, fill=mvoid) +c34 = mcdc.cell(+s2 & -s3 & +s30 & -s31, fill=m2) +c35 = mcdc.cell(+s21 & -s23 & +s30 & -s31, fill=m2) +c36 = mcdc.cell(+s2 & -s23 & +s31 & -s32, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-5.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-5.py new file mode 100644 index 0000000..a13a213 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-5.py @@ -0,0 +1,188 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: Be +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=2.34, bc='interface') +s4 = mcdc.surface('plane-z', z=2.4988, bc='interface') +s5 = mcdc.surface('plane-z', z=2.5242, bc='interface') +s6 = mcdc.surface('plane-z', z=5.5248, bc='interface') +s7 = mcdc.surface('plane-z', z=5.5502, bc='interface') +s8 = mcdc.surface('plane-z', z=5.5756, bc='interface') +s9 = mcdc.surface('plane-z', z=8.5849, bc='interface') +s10 = mcdc.surface('plane-z', z=8.6103, bc='interface') +s11 = mcdc.surface('plane-z', z=9.5509, bc='interface') +s12 = mcdc.surface('plane-z', z=9.5763, bc='interface') +s13 = mcdc.surface('plane-z', z=12.5719, bc='interface') +s14 = mcdc.surface('plane-z', z=12.5973, bc='interface') +s15 = mcdc.surface('plane-z', z=12.6227, bc='interface') +s16 = mcdc.surface('plane-z', z=15.5948, bc='interface') +s17 = mcdc.surface('plane-z', z=15.6202, bc='interface') +s18 = mcdc.surface('plane-z', z=15.779, bc='interface') +s19 = mcdc.surface('plane-z', z=18.119, bc='interface') +s20 = mcdc.surface('plane-z', z=19.9085, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s22 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s23 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=10.0432, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s28, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s24, fill=m5) +c3 = mcdc.cell(+s3 & -s4 & -s23, fill=m3) +c4 = mcdc.cell(+s3 & -s4 & +s23 & -s24, fill=mvoid) +c5 = mcdc.cell(+s4 & -s5 & -s24, fill=m3) +c6 = mcdc.cell(+s5 & -s6 & -s23, fill=m11) +c7 = mcdc.cell(+s5 & -s6 & +s23 & -s24, fill=m3) +c8 = mcdc.cell(+s6 & -s7 & -s24, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & -s24, fill=m3) +c10 = mcdc.cell(+s8 & -s9 & -s23, fill=m14) +c11 = mcdc.cell(+s8 & -s9 & +s23 & -s24, fill=m3) +c12 = mcdc.cell(+s9 & -s10 & -s24, fill=m3) +c13 = mcdc.cell(+s10 & -s11 & -s21, fill=mvoid) +c14 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m1) +c15 = mcdc.cell(+s10 & -s11 & +s22 & -s24, fill=mvoid) +c16 = mcdc.cell(+s11 & -s12 & -s24, fill=m3) +c17 = mcdc.cell(+s12 & -s13 & -s23, fill=m13) +c18 = mcdc.cell(+s12 & -s13 & +s23 & -s24, fill=m3) +c19 = mcdc.cell(+s13 & -s14 & -s24, fill=m3) +c20 = mcdc.cell(+s14 & -s15 & -s24, fill=m3) +c21 = mcdc.cell(+s15 & -s16 & -s23, fill=m12) +c22 = mcdc.cell(+s15 & -s16 & +s23 & -s24, fill=m3) +c23 = mcdc.cell(+s16 & -s17 & -s24, fill=m3) +c24 = mcdc.cell(+s17 & -s18 & -s23, fill=m3) +c25 = mcdc.cell(+s17 & -s18 & +s23 & -s24, fill=mvoid) +c26 = mcdc.cell(+s18 & -s19 & -s24, fill=m5) +c27 = mcdc.cell(+s19 & -s20 & -s24, fill=mvoid) +c28 = mcdc.cell(+s2 & -s20 & +s24 & -s25, fill=mvoid) +c29 = mcdc.cell(+s2 & -s20 & +s25 & -s26, fill=m4) +c30 = mcdc.cell(+s2 & -s20 & +s26 & -s27, fill=mvoid) +c31 = mcdc.cell(+s2 & -s20 & +s27 & -s28, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-6.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-6.py new file mode 100644 index 0000000..9243206 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-6.py @@ -0,0 +1,184 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=2.34, bc='interface') +s4 = mcdc.surface('plane-z', z=2.4988, bc='interface') +s5 = mcdc.surface('plane-z', z=2.5242, bc='interface') +s6 = mcdc.surface('plane-z', z=5.5248, bc='interface') +s7 = mcdc.surface('plane-z', z=5.5502, bc='interface') +s8 = mcdc.surface('plane-z', z=5.5756, bc='interface') +s9 = mcdc.surface('plane-z', z=8.5849, bc='interface') +s10 = mcdc.surface('plane-z', z=8.6103, bc='interface') +s11 = mcdc.surface('plane-z', z=9.1622, bc='interface') +s12 = mcdc.surface('plane-z', z=9.1876, bc='interface') +s13 = mcdc.surface('plane-z', z=12.1832, bc='interface') +s14 = mcdc.surface('plane-z', z=12.2086, bc='interface') +s15 = mcdc.surface('plane-z', z=12.234, bc='interface') +s16 = mcdc.surface('plane-z', z=15.2061, bc='interface') +s17 = mcdc.surface('plane-z', z=15.2315, bc='interface') +s18 = mcdc.surface('plane-z', z=15.3903, bc='interface') +s19 = mcdc.surface('plane-z', z=17.7303, bc='interface') +s20 = mcdc.surface('plane-z', z=19.9085, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s22 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s23 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=10.0609, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s28, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s24, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s23, fill=m3) +c4 = mcdc.cell(+s3 & -s4 & +s23 & -s24, fill=mvoid) +c5 = mcdc.cell(+s4 & -s5 & -s24, fill=m3) +c6 = mcdc.cell(+s5 & -s6 & -s23, fill=m11) +c7 = mcdc.cell(+s5 & -s6 & +s23 & -s24, fill=m3) +c8 = mcdc.cell(+s6 & -s7 & -s24, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & -s24, fill=m3) +c10 = mcdc.cell(+s8 & -s9 & -s23, fill=m14) +c11 = mcdc.cell(+s8 & -s9 & +s23 & -s24, fill=m3) +c12 = mcdc.cell(+s9 & -s10 & -s24, fill=m3) +c13 = mcdc.cell(+s10 & -s11 & -s21, fill=mvoid) +c14 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m1) +c15 = mcdc.cell(+s10 & -s11 & +s22 & -s24, fill=mvoid) +c16 = mcdc.cell(+s11 & -s12 & -s24, fill=m3) +c17 = mcdc.cell(+s12 & -s13 & -s23, fill=m13) +c18 = mcdc.cell(+s12 & -s13 & +s23 & -s24, fill=m3) +c19 = mcdc.cell(+s13 & -s14 & -s24, fill=m3) +c20 = mcdc.cell(+s14 & -s15 & -s24, fill=m3) +c21 = mcdc.cell(+s15 & -s16 & -s23, fill=m12) +c22 = mcdc.cell(+s15 & -s16 & +s23 & -s24, fill=m3) +c23 = mcdc.cell(+s16 & -s17 & -s24, fill=m3) +c24 = mcdc.cell(+s17 & -s18 & -s23, fill=m3) +c25 = mcdc.cell(+s17 & -s18 & +s23 & -s24, fill=mvoid) +c26 = mcdc.cell(+s18 & -s19 & -s24, fill=m2) +c27 = mcdc.cell(+s19 & -s20 & -s24, fill=mvoid) +c28 = mcdc.cell(+s2 & -s20 & +s24 & -s25, fill=mvoid) +c29 = mcdc.cell(+s2 & -s20 & +s25 & -s26, fill=m4) +c30 = mcdc.cell(+s2 & -s20 & +s26 & -s27, fill=mvoid) +c31 = mcdc.cell(+s2 & -s20 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-7.py b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-7.py new file mode 100644 index 0000000..4312aa3 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/mcdc/heu-comp-inter-003_case-7.py @@ -0,0 +1,232 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Aluminum +m1 = mcdc.material(nuclides=[ + ['Al27',0.060239]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',9.736e-05], + ['U238',0.047969]]) +# Material Name: SAE 1020 Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00404865615], + ['Fe56',0.06355524318], + ['Fe57',0.00146776773], + ['Fe58',0.00019533293999999998], + ['C0',0.00054977], + ['Mn55',0.00016969]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: Be +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU, Can I +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.02345], + ['U238',0.0013421], + ['H1',0.07385949533046], + ['H2',1.1504669540000001e-05], + ['O16',0.00085520575413], + ['O17',3.2424587e-07], + ['C0',0.00014562], + ['N14',0.0013543208841], + ['N15',4.9791159e-06], + ['Fe54',2.14377065e-06], + ['Fe56',3.3652614580000005e-05], + ['Fe57',7.7718563e-07], + ['Fe58',1.0342914000000001e-07], + ['Au197',0.0003398]]) +# Material Name: HEU, Can II +# Depletable +m12 = mcdc.material(nuclides=[ + ['U235',0.023409], + ['U238',0.0013371], + ['H1',0.07538425782696001], + ['H2',1.174217304e-05], + ['O16',0.00056681509563], + ['O17',2.1490437000000002e-07], + ['C0',0.00019893], + ['N14',0.00019626842563], + ['N15',7.2157437e-07], + ['Fe54',2.2366477e-06], + ['Fe56',3.5110585640000004e-05], + ['Fe57',8.108565399999999e-07], + ['Fe58',1.0791012000000002e-07], + ['Au197',0.00033787]]) +# Material Name: HEU, Can III +# Depletable +m13 = mcdc.material(nuclides=[ + ['U235',0.02355], + ['U238',0.0013584], + ['H1',0.06990211174938], + ['H2',1.088825062e-05], + ['O16',0.00048405647303999993], + ['O17',1.8352696e-07], + ['C0',0.00015288], + ['N14',0.00020568381028], + ['N15',7.5618972e-07], + ['Fe54',6.058926999999999e-06], + ['Fe56',9.511219639999999e-05], + ['Fe57',2.1965554e-06], + ['Fe58',2.9232119999999997e-07], + ['Au197',0.00034242]]) +# Material Name: HEU, Can IV +# Depletable +m14 = mcdc.material(nuclides=[ + ['U235',0.022939], + ['U238',0.0013117], + ['H1',0.0727136738085], + ['H2',1.13261915e-05], + ['O16',0.00063688852773], + ['O17',2.4147227e-07], + ['C0',0.00015539], + ['N14',0.00024310622800000002], + ['N15',8.93772e-07], + ['Fe54',1.19442575e-06], + ['Fe56',1.8749929900000002e-05], + ['Fe57',4.3301765e-07], + ['Fe58',5.76267e-08], + ['Au197',0.00034196]]) +# Material Name: HEU, Can A +# Depletable +m15 = mcdc.material(nuclides=[ + ['U235',0.02303], + ['U238',0.0013124], + ['H1',0.07027905303540001], + ['H2',1.09469646e-05], + ['O16',0.00060008248251], + ['O17',2.2751749e-07], + ['C0',9.6792e-05], + ['N14',0.00026208644785000006], + ['N15',9.6355215e-07], + ['Fe54',5.25202475e-06], + ['Fe56',8.24455567e-05], + ['Fe57',1.9040274499999997e-06], + ['Fe58',2.533911e-07], + ['Au197',0.00032844]]) +# Material Name: HEU, Can B +# Depletable +m16 = mcdc.material(nuclides=[ + ['U235',0.022951], + ['U238',0.0013058], + ['H1',0.0732285936024], + ['H2',1.14063976e-05], + ['O16',0.0004934129256], + ['O17',1.870744e-07], + ['C0',0.00012804], + ['N14',0.00022934681403], + ['N15',8.4318597e-07], + ['Fe54',3.9574157e-06], + ['Fe56',6.212296324000001e-05], + ['Fe57',1.4346901400000002e-06], + ['Fe58',1.9093092e-07], + ['Au197',0.0003014]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-1.27, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=2.34, bc='interface') +s4 = mcdc.surface('plane-z', z=2.4988, bc='interface') +s5 = mcdc.surface('plane-z', z=2.5198, bc='interface') +s6 = mcdc.surface('plane-z', z=4.5323, bc='interface') +s7 = mcdc.surface('plane-z', z=4.5533, bc='interface') +s8 = mcdc.surface('plane-z', z=4.7121, bc='interface') +s9 = mcdc.surface('plane-z', z=4.7331, bc='interface') +s10 = mcdc.surface('plane-z', z=6.7422, bc='interface') +s11 = mcdc.surface('plane-z', z=6.7632, bc='interface') +s12 = mcdc.surface('plane-z', z=6.7886, bc='interface') +s13 = mcdc.surface('plane-z', z=9.7842, bc='interface') +s14 = mcdc.surface('plane-z', z=9.8096, bc='interface') +s15 = mcdc.surface('plane-z', z=10.8312, bc='interface') +s16 = mcdc.surface('plane-z', z=10.8566, bc='interface') +s17 = mcdc.surface('plane-z', z=13.8287, bc='interface') +s18 = mcdc.surface('plane-z', z=13.8541, bc='interface') +s19 = mcdc.surface('plane-z', z=13.8795, bc='interface') +s20 = mcdc.surface('plane-z', z=16.8801, bc='interface') +s21 = mcdc.surface('plane-z', z=16.9055, bc='interface') +s22 = mcdc.surface('plane-z', z=17.0643, bc='interface') +s23 = mcdc.surface('plane-z', z=19.4043, bc='interface') +s24 = mcdc.surface('plane-z', z=19.9085, bc='vacuum') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.0325, bc='interface') +s26 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.35, bc='interface') +s27 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.505, bc='interface') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5438, bc='interface') +s29 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.5489, bc='interface') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.6759, bc='interface') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.7013, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=10.0609, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s32, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s28, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s27, fill=m3) +c4 = mcdc.cell(+s3 & -s4 & +s27 & -s28, fill=mvoid) +c5 = mcdc.cell(+s4 & -s5 & -s28, fill=m3) +c6 = mcdc.cell(+s5 & -s6 & -s27, fill=m16) +c7 = mcdc.cell(+s5 & -s6 & +s27 & -s28, fill=m3) +c8 = mcdc.cell(+s6 & -s7 & -s28, fill=m3) +c9 = mcdc.cell(+s7 & -s8 & -s27, fill=m3) +c10 = mcdc.cell(+s7 & -s8 & +s27 & -s28, fill=mvoid) +c11 = mcdc.cell(+s8 & -s9 & -s28, fill=m3) +c12 = mcdc.cell(+s9 & -s10 & -s27, fill=m15) +c13 = mcdc.cell(+s9 & -s10 & +s27 & -s28, fill=m3) +c14 = mcdc.cell(+s10 & -s11 & -s28, fill=m3) +c15 = mcdc.cell(+s11 & -s12 & -s28, fill=m3) +c16 = mcdc.cell(+s12 & -s13 & -s27, fill=m13) +c17 = mcdc.cell(+s12 & -s13 & +s27 & -s28, fill=m3) +c18 = mcdc.cell(+s13 & -s14 & -s28, fill=m3) +c19 = mcdc.cell(+s14 & -s15 & -s25, fill=mvoid) +c20 = mcdc.cell(+s14 & -s15 & +s25 & -s26, fill=m1) +c21 = mcdc.cell(+s14 & -s15 & +s26 & -s28, fill=mvoid) +c22 = mcdc.cell(+s15 & -s16 & -s28, fill=m3) +c23 = mcdc.cell(+s16 & -s17 & -s27, fill=m12) +c24 = mcdc.cell(+s16 & -s17 & +s27 & -s28, fill=m3) +c25 = mcdc.cell(+s17 & -s18 & -s28, fill=m3) +c26 = mcdc.cell(+s18 & -s19 & -s28, fill=m3) +c27 = mcdc.cell(+s19 & -s20 & -s27, fill=m11) +c28 = mcdc.cell(+s19 & -s20 & +s27 & -s28, fill=m3) +c29 = mcdc.cell(+s20 & -s21 & -s28, fill=m3) +c30 = mcdc.cell(+s21 & -s22 & -s27, fill=m3) +c31 = mcdc.cell(+s21 & -s22 & +s27 & -s28, fill=mvoid) +c32 = mcdc.cell(+s22 & -s23 & -s28, fill=m2) +c33 = mcdc.cell(+s23 & -s24 & -s28, fill=mvoid) +c34 = mcdc.cell(+s2 & -s24 & +s28 & -s29, fill=mvoid) +c35 = mcdc.cell(+s2 & -s24 & +s29 & -s30, fill=m4) +c36 = mcdc.cell(+s2 & -s24 & +s30 & -s31, fill=mvoid) +c37 = mcdc.cell(+s2 & -s24 & +s31 & -s32, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[9.8803,10.4322], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..f23f44f --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/generate_materials.py @@ -0,0 +1,122 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mat = openmc.Material(15) +mat.name = "HEU, Can A" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4557e-04) +mat.add_nuclide('U235', 2.3030e-02) +mat.add_nuclide('U236', 1.0085e-04) +mat.add_nuclide('U238', 1.3124e-03) +mat.add_element('H', 7.0290e-02) +mat.add_element('O', 6.0031e-04) +mat.add_element('C', 9.6792e-05) +mat.add_element('N', 2.6305e-04) +mat.add_element('Fe', 8.9855e-05) +mat.add_element('Au', 3.2844e-04) +mats.append(mat) + +mat = openmc.Material(16) +mat.name = "HEU, Can B" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5226e-04) +mat.add_nuclide('U235', 2.2951e-02) +mat.add_nuclide('U236', 1.0055e-04) +mat.add_nuclide('U238', 1.3058e-03) +mat.add_element('H', 7.3240e-02) +mat.add_element('O', 4.9360e-04) +mat.add_element('C', 1.2804e-04) +mat.add_element('N', 2.3019e-04) +mat.add_element('Fe', 6.7706e-05) +mat.add_element('Au', 3.0140e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-1/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/geometry.xml new file mode 100644 index 0000000..92ead45 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/geometry.xml @@ -0,0 +1,82 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-1/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/materials.xml new file mode 100644 index 0000000..0360120 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/materials.xml @@ -0,0 +1,142 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-1/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/plots.xml new file mode 100644 index 0000000..7c2cdb9 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 15. + 35. 35. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-1/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..60af9bf --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/generate_materials.py @@ -0,0 +1,129 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Be" +mat.set_density('sum') +mat.add_nuclide('Be9', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mat = openmc.Material(15) +mat.name = "HEU, Can A" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4557e-04) +mat.add_nuclide('U235', 2.3030e-02) +mat.add_nuclide('U236', 1.0085e-04) +mat.add_nuclide('U238', 1.3124e-03) +mat.add_element('H', 7.0290e-02) +mat.add_element('O', 6.0031e-04) +mat.add_element('C', 9.6792e-05) +mat.add_element('N', 2.6305e-04) +mat.add_element('Fe', 8.9855e-05) +mat.add_element('Au', 3.2844e-04) +mats.append(mat) + +mat = openmc.Material(16) +mat.name = "HEU, Can B" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5226e-04) +mat.add_nuclide('U235', 2.2951e-02) +mat.add_nuclide('U236', 1.0055e-04) +mat.add_nuclide('U238', 1.3058e-03) +mat.add_element('H', 7.3240e-02) +mat.add_element('O', 4.9360e-04) +mat.add_element('C', 1.2804e-04) +mat.add_element('N', 2.3019e-04) +mat.add_element('Fe', 6.7706e-05) +mat.add_element('Au', 3.0140e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-2/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/geometry.xml new file mode 100644 index 0000000..a8db2c6 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/geometry.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-2/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/materials.xml new file mode 100644 index 0000000..77023f8 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/materials.xml @@ -0,0 +1,147 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-2/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/plots.xml new file mode 100644 index 0000000..7c2cdb9 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 15. + 35. 35. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-2/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..60af9bf --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/generate_materials.py @@ -0,0 +1,129 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Be" +mat.set_density('sum') +mat.add_nuclide('Be9', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mat = openmc.Material(15) +mat.name = "HEU, Can A" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4557e-04) +mat.add_nuclide('U235', 2.3030e-02) +mat.add_nuclide('U236', 1.0085e-04) +mat.add_nuclide('U238', 1.3124e-03) +mat.add_element('H', 7.0290e-02) +mat.add_element('O', 6.0031e-04) +mat.add_element('C', 9.6792e-05) +mat.add_element('N', 2.6305e-04) +mat.add_element('Fe', 8.9855e-05) +mat.add_element('Au', 3.2844e-04) +mats.append(mat) + +mat = openmc.Material(16) +mat.name = "HEU, Can B" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5226e-04) +mat.add_nuclide('U235', 2.2951e-02) +mat.add_nuclide('U236', 1.0055e-04) +mat.add_nuclide('U238', 1.3058e-03) +mat.add_element('H', 7.3240e-02) +mat.add_element('O', 4.9360e-04) +mat.add_element('C', 1.2804e-04) +mat.add_element('N', 2.3019e-04) +mat.add_element('Fe', 6.7706e-05) +mat.add_element('Au', 3.0140e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-3/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/geometry.xml new file mode 100644 index 0000000..5656142 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/geometry.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-3/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/materials.xml new file mode 100644 index 0000000..77023f8 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/materials.xml @@ -0,0 +1,147 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-3/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/plots.xml new file mode 100644 index 0000000..7c2cdb9 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 15. + 35. 35. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-3/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..60af9bf --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/generate_materials.py @@ -0,0 +1,129 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Be" +mat.set_density('sum') +mat.add_nuclide('Be9', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mat = openmc.Material(15) +mat.name = "HEU, Can A" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4557e-04) +mat.add_nuclide('U235', 2.3030e-02) +mat.add_nuclide('U236', 1.0085e-04) +mat.add_nuclide('U238', 1.3124e-03) +mat.add_element('H', 7.0290e-02) +mat.add_element('O', 6.0031e-04) +mat.add_element('C', 9.6792e-05) +mat.add_element('N', 2.6305e-04) +mat.add_element('Fe', 8.9855e-05) +mat.add_element('Au', 3.2844e-04) +mats.append(mat) + +mat = openmc.Material(16) +mat.name = "HEU, Can B" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5226e-04) +mat.add_nuclide('U235', 2.2951e-02) +mat.add_nuclide('U236', 1.0055e-04) +mat.add_nuclide('U238', 1.3058e-03) +mat.add_element('H', 7.3240e-02) +mat.add_element('O', 4.9360e-04) +mat.add_element('C', 1.2804e-04) +mat.add_element('N', 2.3019e-04) +mat.add_element('Fe', 6.7706e-05) +mat.add_element('Au', 3.0140e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-4/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/geometry.xml new file mode 100644 index 0000000..7d0b591 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/geometry.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-4/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/materials.xml new file mode 100644 index 0000000..77023f8 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/materials.xml @@ -0,0 +1,147 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-4/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/plots.xml new file mode 100644 index 0000000..7c2cdb9 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 15. + 35. 35. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-4/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..60d9bc5 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/generate_materials.py @@ -0,0 +1,99 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Be" +mat.set_density('sum') +mat.add_nuclide('Be9', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-5/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/geometry.xml new file mode 100644 index 0000000..d4e0847 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/geometry.xml @@ -0,0 +1,82 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-5/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/materials.xml new file mode 100644 index 0000000..848616a --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/materials.xml @@ -0,0 +1,109 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-5/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/plots.xml new file mode 100644 index 0000000..8341b79 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 10. + 25. 25. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-5/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..b4aa184 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/generate_materials.py @@ -0,0 +1,92 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-6/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/geometry.xml new file mode 100644 index 0000000..5cb8dde --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/geometry.xml @@ -0,0 +1,84 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-6/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/materials.xml new file mode 100644 index 0000000..8288aaf --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/materials.xml @@ -0,0 +1,104 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-6/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/plots.xml new file mode 100644 index 0000000..8341b79 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 10. + 25. 25. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-6/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-7/generate_materials.py b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..60af9bf --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/generate_materials.py @@ -0,0 +1,129 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_nuclide('Al27', 6.0239e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 9.7360e-05) +mat.add_nuclide('U238', 4.7969e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "SAE 1020 Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.9267e-02) +mat.add_element('C', 5.4977e-04) +mat.add_element('Mn', 1.6969e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Be" +mat.set_density('sum') +mat.add_nuclide('Be9', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "HEU, Can I" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5279e-04) +mat.add_nuclide('U235', 2.3450e-02) +mat.add_nuclide('U236', 1.1027e-04) +mat.add_nuclide('U238', 1.3421e-03) +mat.add_element('H', 7.3871e-02) +mat.add_element('O', 8.5553e-04) +mat.add_element('C', 1.4562e-04) +mat.add_element('N', 1.3593e-03) +mat.add_element('Fe', 3.6677e-05) +mat.add_element('Au', 3.3980e-04) +mats.append(mat) + +mat = openmc.Material(12) +mat.name = "HEU, Can II" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5484e-04) +mat.add_nuclide('U235', 2.3409e-02) +mat.add_nuclide('U236', 1.0757e-04) +mat.add_nuclide('U238', 1.3371e-03) +mat.add_element('H', 7.5396e-02) +mat.add_element('O', 5.6703e-04) +mat.add_element('C', 1.9893e-04) +mat.add_element('N', 1.9699e-04) +mat.add_element('Fe', 3.8266e-05) +mat.add_element('Au', 3.3787e-04) +mats.append(mat) + +mat = openmc.Material(13) +mat.name = "HEU, Can III" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5651e-04) +mat.add_nuclide('U235', 2.3550e-02) +mat.add_nuclide('U236', 1.0829e-04) +mat.add_nuclide('U238', 1.3584e-03) +mat.add_element('H', 6.9913e-02) +mat.add_element('O', 4.8424e-04) +mat.add_element('C', 1.5288e-04) +mat.add_element('N', 2.0644e-04) +mat.add_element('Fe', 1.0366e-04) +mat.add_element('Au', 3.4242e-04) +mats.append(mat) + +mat = openmc.Material(14) +mat.name = "HEU, Can IV" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4873e-04) +mat.add_nuclide('U235', 2.2939e-02) +mat.add_nuclide('U236', 1.0390e-04) +mat.add_nuclide('U238', 1.3117e-03) +mat.add_element('H', 7.2725e-02) +mat.add_element('O', 6.3713e-04) +mat.add_element('C', 1.5539e-04) +mat.add_element('N', 2.4400e-04) +mat.add_element('Fe', 2.0435e-05) +mat.add_element('Au', 3.4196e-04) +mats.append(mat) + +mat = openmc.Material(15) +mat.name = "HEU, Can A" +mat.set_density('sum') +mat.add_nuclide('U234', 2.4557e-04) +mat.add_nuclide('U235', 2.3030e-02) +mat.add_nuclide('U236', 1.0085e-04) +mat.add_nuclide('U238', 1.3124e-03) +mat.add_element('H', 7.0290e-02) +mat.add_element('O', 6.0031e-04) +mat.add_element('C', 9.6792e-05) +mat.add_element('N', 2.6305e-04) +mat.add_element('Fe', 8.9855e-05) +mat.add_element('Au', 3.2844e-04) +mats.append(mat) + +mat = openmc.Material(16) +mat.name = "HEU, Can B" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5226e-04) +mat.add_nuclide('U235', 2.2951e-02) +mat.add_nuclide('U236', 1.0055e-04) +mat.add_nuclide('U238', 1.3058e-03) +mat.add_element('H', 7.3240e-02) +mat.add_element('O', 4.9360e-04) +mat.add_element('C', 1.2804e-04) +mat.add_element('N', 2.3019e-04) +mat.add_element('Fe', 6.7706e-05) +mat.add_element('Au', 3.0140e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-7/geometry.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/geometry.xml new file mode 100644 index 0000000..0bbeebf --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/geometry.xml @@ -0,0 +1,95 @@ + + + + + + filler-B-filler-A-III-gap-II-I-filler + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-7/materials.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/materials.xml new file mode 100644 index 0000000..77023f8 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/materials.xml @@ -0,0 +1,147 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-7/plots.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/plots.xml new file mode 100644 index 0000000..8341b79 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 10. + 25. 25. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-comp-inter-003/openmc/case-7/settings.xml b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/settings.xml new file mode 100644 index 0000000..464c792 --- /dev/null +++ b/icsbep/openmc/heu-comp-inter-003/openmc/case-7/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 9.8803 1 1 10.4322 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-001/mcdc/heu-met-fast-001_case-1.py b/icsbep/openmc/heu-met-fast-001/mcdc/heu-met-fast-001_case-1.py new file mode 100644 index 0000000..4749dee --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/mcdc/heu-met-fast-001_case-1.py @@ -0,0 +1,76 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044936], + ['U238',0.0027213]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.045244], + ['U238',0.0024168]]) +m3 = mcdc.material(nuclides=[ + ['U235',0.045268], + ['U238',0.002393]]) +m4 = mcdc.material(nuclides=[ + ['U235',0.04509], + ['U238',0.002569]]) +m5 = mcdc.material(nuclides=[ + ['U235',0.045239], + ['U238',0.0024215]]) +m6 = mcdc.material(nuclides=[ + ['U235',0.044874], + ['U238',0.0024169]]) +m7 = mcdc.material(nuclides=[ + ['N14',3.5214e-05], + ['O16',1.5092e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.0216, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.0541, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.2809, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.2937, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.7525, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.762, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.2527, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.261, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.7062, bc='interface') +s10 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.7499, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m7) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m7) +c5 = mcdc.cell(+s4 & -s5, fill=m3) +c6 = mcdc.cell(+s5 & -s6, fill=m7) +c7 = mcdc.cell(+s6 & -s7, fill=m4) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +c9 = mcdc.cell(+s8 & -s9, fill=m5) +c10 = mcdc.cell(+s9 & -s10, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-001/mcdc/heu-met-fast-001_case-2.py b/icsbep/openmc/heu-met-fast-001/mcdc/heu-met-fast-001_case-2.py new file mode 100644 index 0000000..9488e8b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/mcdc/heu-met-fast-001_case-2.py @@ -0,0 +1,40 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044994], + ['U238',0.0024984]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.7407, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-001/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-001/openmc/case-1/geometry.xml new file mode 100644 index 0000000..ee2d318 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/openmc/case-1/geometry.xml @@ -0,0 +1,35 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-001/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-001/openmc/case-1/materials.xml new file mode 100644 index 0000000..bab389c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/openmc/case-1/materials.xml @@ -0,0 +1,68 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-001/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-001/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-001/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-001/openmc/case-2/geometry.xml new file mode 100644 index 0000000..fd9cd28 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/openmc/case-2/geometry.xml @@ -0,0 +1,16 @@ + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-001/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-001/openmc/case-2/materials.xml new file mode 100644 index 0000000..829de71 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/openmc/case-2/materials.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-001/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-001/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-001/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-1.py b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-1.py new file mode 100644 index 0000000..0d1080b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-1.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0509, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=26.3709, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-2.py b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-2.py new file mode 100644 index 0000000..b08b001 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-2.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=5.1706, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=25.4906, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-26.035, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-5.715, bc='interface') +s5 = mcdc.surface('plane-z', z=5.715, bc='interface') +s6 = mcdc.surface('plane-z', z=25.035, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c3 = mcdc.cell(+s1 & -s2 & +s4 & -s5, fill=m2) +c4 = mcdc.cell(-s2 & +s5 & -s6, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-3.py b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-3.py new file mode 100644 index 0000000..112cb28 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-3.py @@ -0,0 +1,60 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-25.4, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-5.08, bc='interface') +s3 = mcdc.surface('plane-x', x=5.08, bc='interface') +s4 = mcdc.surface('plane-x', x=25.4, bc='vacuum') +s5 = mcdc.surface('plane-y', y=-25.4, bc='vacuum') +s6 = mcdc.surface('plane-y', y=-5.08, bc='interface') +s7 = mcdc.surface('plane-y', y=5.08, bc='interface') +s8 = mcdc.surface('plane-y', y=25.4, bc='vacuum') +s9 = mcdc.surface('plane-z', z=-24.97, bc='vacuum') +s10 = mcdc.surface('plane-z', z=-4.65, bc='interface') +s11 = mcdc.surface('plane-z', z=4.65, bc='interface') +s12 = mcdc.surface('plane-z', z=24.97, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & +s5 & -s8 & +s9 & -s12, fill=m2) +c2 = mcdc.cell(+s2 & -s3 & +s5 & -s6 & +s9 & -s12, fill=m2) +c3 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s9 & -s10, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s10 & -s11, fill=m1) +c5 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s11 & -s12, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s9 & -s12, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s5 & -s8 & +s9 & -s12, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-4.py b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-4.py new file mode 100644 index 0000000..1f3d17c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-4.py @@ -0,0 +1,60 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-26.67, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-6.35, bc='interface') +s3 = mcdc.surface('plane-x', x=6.35, bc='interface') +s4 = mcdc.surface('plane-x', x=26.67, bc='vacuum') +s5 = mcdc.surface('plane-y', y=-26.67, bc='vacuum') +s6 = mcdc.surface('plane-y', y=-6.35, bc='interface') +s7 = mcdc.surface('plane-y', y=6.35, bc='interface') +s8 = mcdc.surface('plane-y', y=26.67, bc='vacuum') +s9 = mcdc.surface('plane-z', z=-23.5275, bc='vacuum') +s10 = mcdc.surface('plane-z', z=-3.2075, bc='interface') +s11 = mcdc.surface('plane-z', z=3.2075, bc='interface') +s12 = mcdc.surface('plane-z', z=23.5275, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & +s5 & -s8 & +s9 & -s12, fill=m2) +c2 = mcdc.cell(+s2 & -s3 & +s5 & -s6 & +s9 & -s12, fill=m2) +c3 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s9 & -s10, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s10 & -s11, fill=m1) +c5 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s11 & -s12, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s9 & -s12, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s5 & -s8 & +s9 & -s12, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-5.py b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-5.py new file mode 100644 index 0000000..5602519 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-5.py @@ -0,0 +1,60 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-24.13, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-3.81, bc='interface') +s3 = mcdc.surface('plane-x', x=3.81, bc='interface') +s4 = mcdc.surface('plane-x', x=24.13, bc='vacuum') +s5 = mcdc.surface('plane-y', y=-24.13, bc='vacuum') +s6 = mcdc.surface('plane-y', y=-3.81, bc='interface') +s7 = mcdc.surface('plane-y', y=3.81, bc='interface') +s8 = mcdc.surface('plane-y', y=24.13, bc='vacuum') +s9 = mcdc.surface('plane-z', z=-29.9185, bc='vacuum') +s10 = mcdc.surface('plane-z', z=-9.5985, bc='interface') +s11 = mcdc.surface('plane-z', z=9.5985, bc='interface') +s12 = mcdc.surface('plane-z', z=29.9185, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & +s5 & -s8 & +s9 & -s12, fill=m2) +c2 = mcdc.cell(+s2 & -s3 & +s5 & -s6 & +s9 & -s12, fill=m2) +c3 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s9 & -s10, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s10 & -s11, fill=m1) +c5 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s11 & -s12, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s9 & -s12, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s5 & -s8 & +s9 & -s12, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-6.py b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-6.py new file mode 100644 index 0000000..daf2617 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/mcdc/heu-met-fast-002_case-6.py @@ -0,0 +1,60 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-24.13, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-3.81, bc='interface') +s3 = mcdc.surface('plane-x', x=3.81, bc='interface') +s4 = mcdc.surface('plane-x', x=24.13, bc='vacuum') +s5 = mcdc.surface('plane-y', y=-24.765, bc='vacuum') +s6 = mcdc.surface('plane-y', y=-4.445, bc='interface') +s7 = mcdc.surface('plane-y', y=4.445, bc='interface') +s8 = mcdc.surface('plane-y', y=24.765, bc='vacuum') +s9 = mcdc.surface('plane-z', z=-27.9372, bc='vacuum') +s10 = mcdc.surface('plane-z', z=-7.6172, bc='interface') +s11 = mcdc.surface('plane-z', z=7.6172, bc='interface') +s12 = mcdc.surface('plane-z', z=27.9372, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & +s5 & -s8 & +s9 & -s12, fill=m2) +c2 = mcdc.cell(+s2 & -s3 & +s5 & -s6 & +s9 & -s12, fill=m2) +c3 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s9 & -s10, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s10 & -s11, fill=m1) +c5 = mcdc.cell(+s2 & -s3 & +s6 & -s7 & +s11 & -s12, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s9 & -s12, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s5 & -s8 & +s9 & -s12, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-1/geometry.xml new file mode 100644 index 0000000..e6edf61 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-1/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-1/materials.xml new file mode 100644 index 0000000..45285f4 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-1/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-2/geometry.xml new file mode 100644 index 0000000..3461a75 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-2/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-2/materials.xml new file mode 100644 index 0000000..b1b28ad --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-2/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-3/geometry.xml new file mode 100644 index 0000000..c38df34 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-3/geometry.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-3/materials.xml new file mode 100644 index 0000000..b76fb36 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-3/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-3/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-4/geometry.xml new file mode 100644 index 0000000..ce15d68 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-4/geometry.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-4/materials.xml new file mode 100644 index 0000000..08bbfeb --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-4/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-4/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-5/geometry.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-5/geometry.xml new file mode 100644 index 0000000..024caef --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-5/geometry.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-5/materials.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-5/materials.xml new file mode 100644 index 0000000..453685b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-5/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-5/settings.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-5/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-6/geometry.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-6/geometry.xml new file mode 100644 index 0000000..073f93e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-6/geometry.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-6/materials.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-6/materials.xml new file mode 100644 index 0000000..41c64e7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-6/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-002/openmc/case-6/settings.xml b/icsbep/openmc/heu-met-fast-002/openmc/case-6/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-002/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-1.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-1.py new file mode 100644 index 0000000..e0f27f5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-1.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.782, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.862, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-10.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-10.py new file mode 100644 index 0000000..e09c649 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-10.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tungsten carbide +m2 = mcdc.material(nuclides=[ + ['W182',0.012697000000000002], + ['W183',0.0068626], + ['W184',0.014754], + ['W186',0.013744], + ['C0',0.048057]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0509, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.4809, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-11.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-11.py new file mode 100644 index 0000000..204e1a4 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-11.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tungsten carbide +m2 = mcdc.material(nuclides=[ + ['W182',0.012697000000000002], + ['W183',0.0068626], + ['W184',0.014754], + ['W186',0.013744], + ['C0',0.048057]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0159, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.5259, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-12.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-12.py new file mode 100644 index 0000000..6818718 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-12.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.062169186618], + ['Ni60',0.023947459382000002], + ['Ni61',0.0010409794779999999], + ['Ni62',0.0033190980900000004], + ['Ni64',0.0008452764320000001]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.4627, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=26.7827, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-2.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-2.py new file mode 100644 index 0000000..3e0dd67 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-2.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.4423, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.0623, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-3.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-3.py new file mode 100644 index 0000000..77c3ef0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-3.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.2851, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.4451, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-4.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-4.py new file mode 100644 index 0000000..5a05ab7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-4.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.1535, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=18.8535, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-5.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-5.py new file mode 100644 index 0000000..0e25353 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-5.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.074, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=23.854, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-6.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-6.py new file mode 100644 index 0000000..5c1a3c3 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-6.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0509, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=26.3709, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-7.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-7.py new file mode 100644 index 0000000..0ed9193 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-7.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tuballoy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034428], + ['U238',0.04747]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0276, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=33.9676, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-8.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-8.py new file mode 100644 index 0000000..d22362e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-8.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tungsten carbide +m2 = mcdc.material(nuclides=[ + ['W182',0.012697000000000002], + ['W183',0.0068626], + ['W184',0.014754], + ['W186',0.013744], + ['C0',0.048057]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.602, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.428, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-9.py b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-9.py new file mode 100644 index 0000000..ba5028f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/mcdc/heu-met-fast-003_case-9.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044917], + ['U238',0.0025993]]) +# Material Name: Tungsten carbide +m2 = mcdc.material(nuclides=[ + ['W182',0.012697000000000002], + ['W183',0.0068626], + ['W184',0.014754], + ['W186',0.013744], + ['C0',0.048057]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.2527, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.6187, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..9bfaf77 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-1/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 2-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-1/geometry.xml new file mode 100644 index 0000000..92f1896 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-1/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-1/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-10/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..4b7afff --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-10/generate_materials.py @@ -0,0 +1,21 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 4.5-in WC reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +wc = openmc.Material(name="Tungsten carbide") +wc.add_nuclide('W182', 1.2697e-02) +wc.add_nuclide('W183', 6.8626e-03) +wc.add_nuclide('W184', 1.4754e-02) +wc.add_nuclide('W186', 1.3744e-02) +wc.add_element('C', 4.8057e-02) + +materials = openmc.Materials([oralloy, wc]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-10/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-10/geometry.xml new file mode 100644 index 0000000..303df70 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-10/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-10/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-10/materials.xml new file mode 100644 index 0000000..d9c5bd2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-10/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-10/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-10/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-10/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-11/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-11/generate_materials.py new file mode 100644 index 0000000..54e83a9 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-11/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Oralloy" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9210e-04) +mat.add_nuclide('U235', 4.4917e-02) +mat.add_nuclide('U238', 2.5993e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Tungsten carbide" +mat.set_density('sum') +mat.add_nuclide('W182', 1.2697e-02) +mat.add_nuclide('W183', 6.8626e-03) +mat.add_nuclide('W184', 1.4754e-02) +mat.add_nuclide('W186', 1.3744e-02) +mat.add_element('C', 4.8057e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-11/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-11/geometry.xml new file mode 100644 index 0000000..9d1e1e5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-11/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-11/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-11/materials.xml new file mode 100644 index 0000000..37693ca --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-11/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-11/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-11/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-11/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-12/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-12/generate_materials.py new file mode 100644 index 0000000..094190a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-12/generate_materials.py @@ -0,0 +1,19 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Oralloy" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9210e-4) +mat.add_nuclide('U235', 4.4917e-2) +mat.add_nuclide('U238', 2.5993e-3) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1322e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-12/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-12/geometry.xml new file mode 100644 index 0000000..7a5aa2a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-12/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-12/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-12/materials.xml new file mode 100644 index 0000000..021da99 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-12/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-12/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-12/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-12/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..494686d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-2/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 3-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-2/geometry.xml new file mode 100644 index 0000000..54a1314 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-2/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-2/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..73d0ada --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-3/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 4-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-3/geometry.xml new file mode 100644 index 0000000..74e0c5e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-3/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-3/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..d9ba12c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-4/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 5-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-4/geometry.xml new file mode 100644 index 0000000..13c1af6 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-4/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-4/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-4/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..8b923ff --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-5/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 7-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-5/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-5/geometry.xml new file mode 100644 index 0000000..1d125f3 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-5/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-5/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-5/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-5/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-5/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-5/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..33fde19 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-6/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 8-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-6/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-6/geometry.xml new file mode 100644 index 0000000..5f2fc6a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-6/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-6/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-6/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-6/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-6/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-6/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-7/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..ae8c019 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-7/generate_materials.py @@ -0,0 +1,19 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 11-in Tuballoy reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +tuballoy = openmc.Material(name="Tuballoy") +tuballoy.add_nuclide('U234', 2.6299e-06) +tuballoy.add_nuclide('U235', 3.4428e-04) +tuballoy.add_nuclide('U238', 4.7470e-02) + +materials = openmc.Materials([oralloy, tuballoy]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-7/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-7/geometry.xml new file mode 100644 index 0000000..c7079a7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-7/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-7/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-7/materials.xml new file mode 100644 index 0000000..af17516 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-7/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-7/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-7/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-7/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-8/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..35250b7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-8/generate_materials.py @@ -0,0 +1,21 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 1.9-in WC reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +wc = openmc.Material(name="Tungsten carbide") +wc.add_nuclide('W182', 1.2697e-02) +wc.add_nuclide('W183', 6.8626e-03) +wc.add_nuclide('W184', 1.4754e-02) +wc.add_nuclide('W186', 1.3744e-02) +wc.add_element('C', 4.8057e-02) + +materials = openmc.Materials([oralloy, wc]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-8/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-8/geometry.xml new file mode 100644 index 0000000..0027c86 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-8/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-8/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-8/materials.xml new file mode 100644 index 0000000..d9c5bd2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-8/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-8/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-8/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-8/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-9/generate_materials.py b/icsbep/openmc/heu-met-fast-003/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..30f6610 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-9/generate_materials.py @@ -0,0 +1,21 @@ +""" +Description: Topsy Reflected Oralloy Spherical Assembly +Case: HEU-MET-FAST-003 2.9-in WC reflector +""" + +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide('U234', 4.9210e-04) +oralloy.add_nuclide('U235', 4.4917e-02) +oralloy.add_nuclide('U238', 2.5993e-03) + +wc = openmc.Material(name="Tungsten carbide") +wc.add_nuclide('W182', 1.2697e-02) +wc.add_nuclide('W183', 6.8626e-03) +wc.add_nuclide('W184', 1.4754e-02) +wc.add_nuclide('W186', 1.3744e-02) +wc.add_element('C', 4.8057e-02) + +materials = openmc.Materials([oralloy, wc]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-9/geometry.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-9/geometry.xml new file mode 100644 index 0000000..2a047ce --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-9/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-9/materials.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-9/materials.xml new file mode 100644 index 0000000..d9c5bd2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-9/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-003/openmc/case-9/settings.xml b/icsbep/openmc/heu-met-fast-003/openmc/case-9/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-003/openmc/case-9/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-004/mcdc/heu-met-fast-004_case-1.py b/icsbep/openmc/heu-met-fast-004/mcdc/heu-met-fast-004_case-1.py new file mode 100644 index 0000000..feb2bd0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-004/mcdc/heu-met-fast-004_case-1.py @@ -0,0 +1,65 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Oralloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.047033], + ['U238',0.00047782]]) +# Material Name: Lucite +# S(a,b): c_H_in_H2O (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['H1',0.05774499999999999], + ['C0',0.03609], + ['O16',0.014435000000000002]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066807], + ['O16',0.033403]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5537, bc='interface') +s2 = mcdc.surface('plane-z', z=-32.5, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-7.752, bc='interface') +s4 = mcdc.surface('plane-z', z=-5.212, bc='interface') +s5 = mcdc.surface('plane-z', z=23.054, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.974, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.7, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & +s1 & -s8, fill=m3) +c3 = mcdc.cell(+s3 & -s4 & +s1 & -s6, fill=m3) +c4 = mcdc.cell(+s3 & -s4 & +s6 & -s7, fill=m2) +c5 = mcdc.cell(+s3 & -s4 & +s7 & -s8, fill=m3) +c6 = mcdc.cell(+s4 & -s5 & +s1 & -s8, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-004/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-004/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..6e04c02 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-004/openmc/case-1/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +oralloy = openmc.Material(name="Oralloy") +oralloy.add_nuclide("U234", 5.3678e-4) +oralloy.add_nuclide("U235", 4.7033e-2) +oralloy.add_nuclide("U236", 9.5896e-5) +oralloy.add_nuclide("U238", 4.7782e-4) + +lucite = openmc.Material(name="Lucite") +lucite.add_nuclide("H1", 5.7745e-2) +lucite.add_element("C", 3.6090e-2) +lucite.add_nuclide("O16", 1.4435e-2) +lucite.add_s_alpha_beta("c_H_in_H2O") + +water = openmc.Material(name="Water") +water.add_nuclide("H1", 6.6807e-2) +water.add_nuclide("O16", 3.3403e-2) +water.add_s_alpha_beta("c_H_in_H2O") + +materials = openmc.Materials([oralloy, lucite, water]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-004/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-004/openmc/case-1/geometry.xml new file mode 100644 index 0000000..70331de --- /dev/null +++ b/icsbep/openmc/heu-met-fast-004/openmc/case-1/geometry.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-004/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-004/openmc/case-1/materials.xml new file mode 100644 index 0000000..3e7242e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-004/openmc/case-1/materials.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-004/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-004/openmc/case-1/settings.xml new file mode 100644 index 0000000..4095337 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-004/openmc/case-1/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -1.0 -1.0 -1.0 + 1.0 1.0 1.0 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-008/mcdc/heu-met-fast-008.py b/icsbep/openmc/heu-met-fast-008/mcdc/heu-met-fast-008.py new file mode 100644 index 0000000..ced07f3 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-008/mcdc/heu-met-fast-008.py @@ -0,0 +1,124 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Core, R < 9.15 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041031], + ['U238',0.0041021], + ['C0',0.00038642], + ['Fe54',7.926989e-06], + ['Fe56',0.0001244367748], + ['Fe57',2.8737878e-06], + ['Fe58',3.824484e-07], + ['W180',1.4897999999999999e-08], + ['W182',3.289975e-06], + ['W183',1.7765865000000004e-06], + ['W184',3.8039560000000004e-06], + ['W186',3.5295845000000006e-06], + ['Cu63',0.0004911793650000001], + ['Cu65',0.000219130635], + ['Ni58',0.00022438827009], + ['Ni60',8.643395990999999e-05], + ['Ni61',3.75722439e-06], + ['Ni62',1.1979675450000002e-05], + ['Ni64',3.0508701600000005e-06]]) +# Material Name: Core, outer shell +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.042698], + ['U238',0.0040143], + ['C0',0.00014403], + ['Fe54',2.2194634000000003e-06], + ['Fe56',3.484082888e-05], + ['Fe57',8.046266800000001e-07], + ['Fe58',1.0708103999999999e-07], + ['W180',7.28496e-10], + ['W182',1.608762e-07], + ['W183',8.6873148e-08], + ['W184',1.8600931200000003e-07], + ['W186',1.7259284399999998e-07], + ['Al27',0.00054473]]) +# Material Name: Steel (pure Fe) +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: M1 copper (pure Cu) +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=2.0, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 1.207], radius=2.0, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 1.207], radius=9.15, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.15, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 1.207], radius=10.15, bc='interface') +s7 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s8 = mcdc.surface('cylinder-y', center=[0.0, 1.207], radius=0.6, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.44, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=1.007, bc='interface') +s12 = mcdc.surface('plane-z', z=1.207, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.7, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s15 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.0, bc='vacuum') +s16 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.8, bc='interface') +s18 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.29, bc='interface') +s19 = mcdc.surface('plane-z', z=-14.74, bc='interface') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s10, fill=mvoid) +c2 = mcdc.cell(+s12 & -s2, fill=mvoid) +c3 = mcdc.cell(+s1 & -s3 & +s7 & -s10, fill=m1) +c4 = mcdc.cell(+s2 & -s4 & +s8 & +s12 & +s16, fill=m1) +c5 = mcdc.cell(+s3 & -s5 & -s10 & +s16, fill=m2) +c6 = mcdc.cell(+s4 & -s6 & +s12 & +s16, fill=m2) +c7 = mcdc.cell(+s1 & -s3 & -s7 & -s10, fill=mvoid) +c8 = mcdc.cell(+s2 & -s4 & -s8 & +s12, fill=mvoid) +c9 = mcdc.cell(+s10 & -s11 & -s15, fill=mvoid) +c10 = mcdc.cell(+s11 & -s12 & -s20 & +s17, fill=m3) +c11 = mcdc.cell(+s5 & -s15 & -s10 & +s13, fill=mvoid) +c12 = mcdc.cell(+s6 & -s15 & +s12, fill=mvoid) +c13 = mcdc.cell(+s18 & -s9 & -s13 & -s10, fill=m4) +c14 = mcdc.cell(+s9 & +s19 & -s14 & -s10, fill=m3) +c15 = mcdc.cell(+s9 & -s15 & +s14 & -s13 & -s10, fill=mvoid) +c16 = mcdc.cell(+s3 & -s5 & -s16 & -s10, fill=mvoid) +c17 = mcdc.cell(+s2 & -s6 & -s16 & +s12, fill=mvoid) +c18 = mcdc.cell(+s11 & -s12 & -s17, fill=mvoid) +c19 = mcdc.cell(+s5 & -s13 & -s18 & -s10, fill=mvoid) +c20 = mcdc.cell(-s14 & -s15 & -s19, fill=mvoid) +c21 = mcdc.cell(+s11 & -s12 & -s15 & +s20, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-008/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-008/openmc/generate_materials.py new file mode 100644 index 0000000..3e97801 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-008/openmc/generate_materials.py @@ -0,0 +1,44 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Core, R < 9.15" +mat.set_density('sum') +mat.add_nuclide('U235', 4.1031e-02) +mat.add_nuclide('U238', 4.1021e-03) +mat.add_nuclide('U234', 5.2273e-04) +mat.add_nuclide('U236', 8.8071e-05) +mat.add_element('C', 3.8642e-04) +mat.add_element('Fe', 1.3562e-04) +mat.add_element('W', 1.2415e-05) +mat.add_element('Cu', 7.1031e-04) +mat.add_element('Ni', 3.2961e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Core, outer shell" +mat.set_density('sum') +mat.add_nuclide('U235', 4.2698e-02) +mat.add_nuclide('U238', 4.0143e-03) +mat.add_nuclide('U234', 5.3154e-04) +mat.add_nuclide('U236', 1.7489e-04) +mat.add_element('C', 1.4403e-04) +mat.add_element('Fe', 3.7972e-05) +mat.add_element('W', 6.0708e-07) +mat.add_element('Al', 5.4473e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel (pure Fe)" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "M1 copper (pure Cu)" +mat.set_density('sum') +mat.add_element('Cu', 8.2365e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-008/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-008/openmc/geometry.xml new file mode 100644 index 0000000..9f2520b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-008/openmc/geometry.xml @@ -0,0 +1,56 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-008/openmc/materials.xml b/icsbep/openmc/heu-met-fast-008/openmc/materials.xml new file mode 100644 index 0000000..1e9f085 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-008/openmc/materials.xml @@ -0,0 +1,57 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-008/openmc/settings.xml b/icsbep/openmc/heu-met-fast-008/openmc/settings.xml new file mode 100644 index 0000000..011acd2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-008/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-009/mcdc/heu-met-fast-009_case-1.py b/icsbep/openmc/heu-met-fast-009/mcdc/heu-met-fast-009_case-1.py new file mode 100644 index 0000000..bb4675d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/mcdc/heu-met-fast-009_case-1.py @@ -0,0 +1,119 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041], + ['U238',0.0040977], + ['C0',0.00039932], + ['Fe54',7.9088695e-06], + ['Fe56',0.00012415233740000002], + ['Fe57',2.8672189000000002e-06], + ['Fe58',3.815742e-07], + ['W180',1.4934e-08], + ['W182',3.297925e-06], + ['W183',1.7808795000000001e-06], + ['W184',3.8131480000000004e-06], + ['W186',3.5381135e-06], + ['Cu63',0.00050710461], + ['Cu65',0.00022623539], + ['Ni58',0.00023165888300999998], + ['Ni60',8.923458698999999e-05], + ['Ni61',3.87896571e-06], + ['Ni62',1.236784005e-05], + ['Ni64',3.14972424e-06]]) +# Material Name: Be Reflector +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.1208], + ['O16',8.202190191299999e-05], + ['O17',3.1098086999999996e-08], + ['C0',0.00010019], + ['Fe54',2.9769754e-06], + ['Fe56',4.673214728e-05], + ['Fe57',1.07924908e-06], + ['Fe58',1.4362824e-07]]) +# Material Name: Fe +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Copper +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.75, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 2.06], radius=7.55, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 2.06], radius=8.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 2.06], radius=11.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.15, bc='interface') +s9 = mcdc.surface('plane-z', z=0.0, bc='interface') +s10 = mcdc.surface('plane-z', z=1.86, bc='interface') +s11 = mcdc.surface('plane-z', z=2.06, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.7, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.0, bc='vacuum') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1, bc='interface') +s16 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s17 = mcdc.surface('cylinder-y', center=[0.0, 2.06], radius=0.6, bc='interface') +s18 = mcdc.surface('plane-z', z=-0.15, bc='interface') +s19 = mcdc.surface('plane-z', z=2.21, bc='interface') +s20 = mcdc.surface('plane-z', z=-14.15, bc='vacuum') +s21 = mcdc.surface('plane-z', z=14.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s16 & -s2, fill=mvoid) +c2 = mcdc.cell(-s15 & +s5 & -s7 & +s11, fill=mvoid) +c3 = mcdc.cell(-s2 & +s16, fill=m1) +c4 = mcdc.cell(+s2 & -s3 & +s11, fill=mvoid) +c5 = mcdc.cell(+s2 & -s4 & -s9 & +s16, fill=m1) +c6 = mcdc.cell(+s3 & -s5 & +s11 & +s17, fill=m1) +c7 = mcdc.cell(+s4 & -s6 & -s18, fill=m2) +c8 = mcdc.cell(+s5 & -s7 & +s19 & +s15, fill=m2) +c9 = mcdc.cell(+s2 & +s9 & -s10 & -s14, fill=mvoid) +c10 = mcdc.cell(+s1 & +s10 & -s11 & -s14, fill=m3) +c11 = mcdc.cell(+s6 & -s14 & -s9 & +s12 & +s20, fill=mvoid) +c12 = mcdc.cell(+s7 & -s14 & +s11 & -s21, fill=mvoid) +c13 = mcdc.cell(+s6 & -s8 & -s12 & -s9, fill=m4) +c14 = mcdc.cell(+s8 & -s14 & -s13 & -s9 & +s20, fill=m3) +c15 = mcdc.cell(+s8 & -s14 & +s13 & -s12 & -s9 & +s20, fill=mvoid) +c16 = mcdc.cell(+s2 & -s1 & +s10 & -s11, fill=mvoid) +c17 = mcdc.cell(+s4 & -s6 & +s18 & -s9, fill=mvoid) +c18 = mcdc.cell(+s5 & -s7 & +s11 & -s19, fill=mvoid) +c19 = mcdc.cell(-s9 & +s2 & -s4 & -s16, fill=mvoid) +c20 = mcdc.cell(+s3 & -s5 & +s11 & -s17, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-009/mcdc/heu-met-fast-009_case-2.py b/icsbep/openmc/heu-met-fast-009/mcdc/heu-met-fast-009_case-2.py new file mode 100644 index 0000000..1c72afb --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/mcdc/heu-met-fast-009_case-2.py @@ -0,0 +1,117 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041011], + ['U238',0.0040989], + ['C0',0.00039946], + ['Fe54',7.911792e-06], + ['Fe56',0.0001241982144], + ['Fe57',2.8682784e-06], + ['Fe58',3.8171520000000006e-07], + ['W180',1.4939999999999997e-08], + ['W182',3.29925e-06], + ['W183',1.7815949999999997e-06], + ['W184',3.81468e-06], + ['W186',3.5395349999999996e-06], + ['Cu63',0.00050432478], + ['Cu65',0.00022499521999999998], + ['Ni58',0.00023039265267000002], + ['Ni60',8.874683733000001e-05], + ['Ni61',3.85776357e-06], + ['Ni62',1.230023835e-05], + ['Ni64',3.1325080799999997e-06]]) +# Material Name: BeO Reflector +# S(a,b): c_Be_in_BeO (Not Implemented) +# S(a,b): c_O_in_BeO (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.067634], + ['O16',0.067608366714], + ['O17',2.5633286e-05]]) +# Material Name: Fe +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Copper +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.75, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 2.74], radius=7.55, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 2.74], radius=8.35, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 2.74], radius=11.0, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.15, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=2.54, bc='interface') +s12 = mcdc.surface('plane-z', z=2.74, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.7, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.0, bc='vacuum') +s16 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1, bc='interface') +s17 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s18 = mcdc.surface('cylinder-y', center=[0.0, 2.74], radius=0.6, bc='interface') +s19 = mcdc.surface('plane-z', z=-0.15, bc='interface') +s20 = mcdc.surface('plane-z', z=2.89, bc='interface') +s21 = mcdc.surface('plane-z', z=-14.15, bc='vacuum') +s22 = mcdc.surface('plane-z', z=14.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s3 & -s17, fill=mvoid) +c2 = mcdc.cell(-s16 & +s6 & -s8 & +s12, fill=mvoid) +c3 = mcdc.cell(+s1 & -s3 & +s17, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s12, fill=mvoid) +c5 = mcdc.cell(+s3 & -s5 & -s10 & +s17, fill=m1) +c6 = mcdc.cell(+s4 & -s6 & +s12 & +s18, fill=m1) +c7 = mcdc.cell(+s5 & -s7 & -s19, fill=m2) +c8 = mcdc.cell(+s6 & -s8 & +s20 & +s16, fill=m2) +c9 = mcdc.cell(+s3 & +s10 & -s11 & -s15, fill=mvoid) +c10 = mcdc.cell(+s2 & +s11 & -s12 & -s15, fill=m3) +c11 = mcdc.cell(+s7 & -s15 & -s10 & +s13 & +s21, fill=mvoid) +c12 = mcdc.cell(+s8 & -s15 & +s12 & -s22, fill=mvoid) +c13 = mcdc.cell(+s7 & -s9 & -s13 & -s10, fill=m4) +c14 = mcdc.cell(+s9 & +s21 & -s14 & -s10, fill=m3) +c15 = mcdc.cell(+s9 & -s15 & +s14 & -s13 & -s10 & +s21, fill=mvoid) +c16 = mcdc.cell(+s3 & -s2 & +s11 & -s12, fill=mvoid) +c17 = mcdc.cell(+s5 & -s7 & +s19 & -s10, fill=mvoid) +c18 = mcdc.cell(+s6 & -s8 & +s12 & -s20, fill=mvoid) +c19 = mcdc.cell(-s10 & +s3 & -s5 & -s17, fill=mvoid) +c20 = mcdc.cell(+s4 & -s6 & +s12 & -s18, fill=mvoid) +c21 = mcdc.cell(-s1, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-009/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..725d45c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-1/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2195e-04) +mat.add_nuclide('U235', 4.1000e-02) +mat.add_nuclide('U236', 8.8422e-05) +mat.add_nuclide('U238', 4.0977e-03) +mat.add_element('C', 3.9932e-04) +mat.add_element('Fe', 1.3531e-04) +mat.add_element('W', 1.2445e-05) +mat.add_element('Cu', 7.3334e-04) +mat.add_element('Ni', 3.4029e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Be Reflector" +mat.set_density('sum') +mat.add_element('Be', 1.2080e-01) +mat.add_element('O', 8.2053e-05) +mat.add_element('C', 1.0019e-04) +mat.add_element('Fe', 5.0932e-05) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Copper" +mat.set_density('sum') +mat.add_element('Cu', 8.2365e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-1/geometry.xml new file mode 100644 index 0000000..79e231c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-1/geometry.xml @@ -0,0 +1,56 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-1/materials.xml new file mode 100644 index 0000000..5466098 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-1/materials.xml @@ -0,0 +1,51 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-1/plots.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-1/plots.xml new file mode 100644 index 0000000..a3fccd0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-1/plots.xml @@ -0,0 +1,20 @@ + + + + + mat + yz + 0. 0. 0. + 35 35 + 1000 1000 + + + + cell + yz + 0. 0. 0. + 35 35 + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-1/settings.xml new file mode 100644 index 0000000..fe5799f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1. -1. -1. 1. 1. 1. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-009/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..0962ff6 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-2/generate_materials.py @@ -0,0 +1,40 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2209e-04) +mat.add_nuclide('U235', 4.1011e-02) +mat.add_nuclide('U236', 8.8453e-05) +mat.add_nuclide('U238', 4.0989e-03) +mat.add_element('C', 3.9946e-04) +mat.add_element('Fe', 1.3536e-04) +mat.add_element('W', 1.2450e-05) +mat.add_element('Cu', 7.2932e-04) +mat.add_element('Ni', 3.3843e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "BeO Reflector" +mat.set_density('sum') +mat.add_element('Be', 6.7634e-02) +mat.add_element('O', 6.7634e-02) +mat.add_s_alpha_beta('c_Be_in_BeO') +mat.add_s_alpha_beta('c_O_in_BeO') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Copper" +mat.set_density('sum') +mat.add_element('Cu', 8.2365e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-2/geometry.xml new file mode 100644 index 0000000..beafd83 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-2/geometry.xml @@ -0,0 +1,58 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-2/materials.xml new file mode 100644 index 0000000..239a048 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-2/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-2/plots.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-2/plots.xml new file mode 100644 index 0000000..a3fccd0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-2/plots.xml @@ -0,0 +1,20 @@ + + + + + mat + yz + 0. 0. 0. + 35 35 + 1000 1000 + + + + cell + yz + 0. 0. 0. + 35 35 + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-009/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-009/openmc/case-2/settings.xml new file mode 100644 index 0000000..fe5799f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-009/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1. -1. -1. 1. 1. 1. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-011/mcdc/heu-met-fast-011.py b/icsbep/openmc/heu-met-fast-011/mcdc/heu-met-fast-011.py new file mode 100644 index 0000000..2a05705 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-011/mcdc/heu-met-fast-011.py @@ -0,0 +1,88 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041018], + ['U238',0.0040942], + ['C0',0.0004045000000000001], + ['Fe54',8.3413995e-06], + ['Fe56',0.0001309421334], + ['Fe57',3.0240248999999995e-06], + ['Fe58',4.024422e-07], + ['W180',1.4873999999999998e-08], + ['W182',3.2846750000000004e-06], + ['W183',1.7737245000000002e-06], + ['W184',3.7978280000000002e-06], + ['W186',3.5238985000000003e-06], + ['Cu63',0.000524786265], + ['Cu65',0.00023412373500000003], + ['Ni58',0.00023973961104], + ['Ni60',9.234726896e-05], + ['Ni61',4.01427184e-06], + ['Ni62',1.2799255200000001e-05], + ['Ni64',3.25959296e-06]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.039047], + ['H1',0.078094]]) +# Material Name: Fe +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=2.0, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 1.96], radius=7.55, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.5, bc='interface') +s5 = mcdc.surface('plane-z', z=1.66, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=18.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 1.96], radius=18.0, bc='interface') +s8 = mcdc.surface('plane-z', z=0.0, bc='interface') +s9 = mcdc.surface('plane-z', z=1.96, bc='interface') +s10 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=21.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3 & +s9, fill=mvoid) +c4 = mcdc.cell(+s2 & -s4 & +s5 & -s9, fill=mvoid) +c5 = mcdc.cell(+s2 & -s5 & +s8 & -s10, fill=mvoid) +c6 = mcdc.cell(+s2 & -s6 & -s8, fill=m2) +c7 = mcdc.cell(+s3 & -s7 & +s9, fill=m2) +c8 = mcdc.cell(+s4 & +s5 & -s9 & -s10, fill=m3) +c9 = mcdc.cell(+s6 & -s8 & -s10, fill=mvoid) +c10 = mcdc.cell(+s7 & +s9 & -s10, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-011/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-011/openmc/generate_materials.py new file mode 100644 index 0000000..ac6561b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-011/openmc/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1969e-04) +mat.add_nuclide('U235', 4.1018e-02) +mat.add_nuclide('U236', 8.9938e-05) +mat.add_nuclide('U238', 4.0942e-03) +mat.add_element('C', 4.0450e-04) +mat.add_element('Fe', 1.4271e-04) +mat.add_element('W', 1.2395e-05) +mat.add_element('Cu', 7.5891e-04) +mat.add_element('Ni', 3.5216e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9047e-02) +mat.add_nuclide('H1', 7.8094e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-011/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-011/openmc/geometry.xml new file mode 100644 index 0000000..096c48b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-011/openmc/geometry.xml @@ -0,0 +1,35 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-011/openmc/materials.xml b/icsbep/openmc/heu-met-fast-011/openmc/materials.xml new file mode 100644 index 0000000..6ca210b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-011/openmc/materials.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-011/openmc/plots.xml b/icsbep/openmc/heu-met-fast-011/openmc/plots.xml new file mode 100644 index 0000000..1eecd3c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-011/openmc/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 0. + 50. 50. + 1000 1000 + + + diff --git a/icsbep/openmc/heu-met-fast-011/openmc/settings.xml b/icsbep/openmc/heu-met-fast-011/openmc/settings.xml new file mode 100644 index 0000000..fe5799f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-011/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1. -1. -1. 1. 1. 1. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-012/mcdc/heu-met-fast-012.py b/icsbep/openmc/heu-met-fast-012/mcdc/heu-met-fast-012.py new file mode 100644 index 0000000..8d7705b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-012/mcdc/heu-met-fast-012.py @@ -0,0 +1,101 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.040999], + ['U238',0.0040989], + ['C0',0.00038652], + ['Fe54',7.916468e-06], + ['Fe56',0.0001242716176], + ['Fe57',2.8699736e-06], + ['Fe58',3.819408e-07], + ['W180',1.4896799999999998e-08], + ['W182',3.2897100000000003e-06], + ['W183',1.7764434000000001e-06], + ['W184',3.8036496e-06], + ['W186',3.5293002000000005e-06], + ['Cu63',0.000498218835], + ['Cu65',0.00022227116499999998], + ['Ni58',0.00022760149976999998], + ['Ni60',8.767169023e-05], + ['Ni61',3.8110276699999994e-06], + ['Ni62',1.215122385e-05], + ['Ni64',3.0945584799999997e-06]]) +# Material Name: Aluminum reflector +m2 = mcdc.material(nuclides=[ + ['Al27',0.058566]]) +# Material Name: Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Copper +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.75, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 1.17], radius=7.55, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 1.17], radius=9.15, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 1.17], radius=12.0, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.15, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=1.17, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.7, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s14 = mcdc.surface('plane-y', y=0.5, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.0, bc='vacuum') +s16 = mcdc.surface('plane-y', y=-0.5, bc='interface') +s17 = mcdc.surface('plane-z', z=0.97, bc='interface') +s18 = mcdc.surface('cylinder-y', center=[0.0, 1.17], radius=0.6, bc='interface') +s19 = mcdc.surface('plane-z', z=-14.15, bc='vacuum') +s20 = mcdc.surface('plane-z', z=14.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s3, fill=m1) +c2 = mcdc.cell(+s1 & +s3 & -s5 & -s10, fill=m1) +c3 = mcdc.cell(+s4 & -s6 & +s11 & +s18, fill=m1) +c4 = mcdc.cell(+s5 & -s7 & -s10, fill=m2) +c5 = mcdc.cell(+s6 & -s8 & +s11, fill=m2) +c6 = mcdc.cell(+s7 & -s9 & -s12 & -s10, fill=m4) +c7 = mcdc.cell(+s2 & -s11 & -s15 & +s17, fill=m3) +c8 = mcdc.cell(+s9 & +s19 & -s13 & -s10, fill=m3) +c9 = mcdc.cell(-s1 & -s14 & +s16, fill=mvoid) +c10 = mcdc.cell(-s1 & +s3 & -s5 & -s10, fill=mvoid) +c11 = mcdc.cell(+s3 & -s4 & +s11, fill=mvoid) +c12 = mcdc.cell(+s3 & -s11 & +s17 & -s2, fill=mvoid) +c13 = mcdc.cell(+s7 & -s10 & +s12 & -s15 & +s19, fill=mvoid) +c14 = mcdc.cell(+s8 & +s11 & -s15 & -s20, fill=mvoid) +c15 = mcdc.cell(+s9 & -s12 & +s13 & -s10 & -s15 & +s19, fill=mvoid) +c16 = mcdc.cell(+s4 & -s6 & +s11 & -s18, fill=mvoid) +c17 = mcdc.cell(+s3 & +s10 & -s15 & -s17, fill=mvoid) +c18 = mcdc.cell(-s3 & -s1 & +s14, fill=m1) +c19 = mcdc.cell(-s3 & -s1 & -s16, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# eigenvalue = + +# Simulation Parameters diff --git a/icsbep/openmc/heu-met-fast-012/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-012/openmc/generate_materials.py new file mode 100644 index 0000000..cc1903b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-012/openmc/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.0999e-02) +mat.add_nuclide('U238', 4.0989e-03) +mat.add_nuclide('U234', 5.2246e-04) +mat.add_nuclide('U236', 8.7970e-05) +mat.add_element('C', 3.8652e-04) +mat.add_element('Fe', 1.3544e-04) +mat.add_element('W', 1.2414e-05) +mat.add_element('Cu', 7.2049e-04) +mat.add_element('Ni', 3.3433e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum reflector" +mat.set_density('sum') +mat.add_element('Al', 5.8566e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Copper" +mat.set_density('sum') +mat.add_element('Cu', 8.2365e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-012/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-012/openmc/geometry.xml new file mode 100644 index 0000000..663b7ac --- /dev/null +++ b/icsbep/openmc/heu-met-fast-012/openmc/geometry.xml @@ -0,0 +1,52 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-012/openmc/materials.xml b/icsbep/openmc/heu-met-fast-012/openmc/materials.xml new file mode 100644 index 0000000..4048fae --- /dev/null +++ b/icsbep/openmc/heu-met-fast-012/openmc/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-012/openmc/plots.xml b/icsbep/openmc/heu-met-fast-012/openmc/plots.xml new file mode 100644 index 0000000..ddc8122 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-012/openmc/plots.xml @@ -0,0 +1,18 @@ + + + + + yz + 0. 0. 0. + 30. 30. + 500 500 + + + + yz + 0. 0. 0. + 30. 30. + 500 500 + + + diff --git a/icsbep/openmc/heu-met-fast-012/openmc/settings.xml b/icsbep/openmc/heu-met-fast-012/openmc/settings.xml new file mode 100644 index 0000000..96d1d07 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-012/openmc/settings.xml @@ -0,0 +1,19 @@ + + + + + + + 3000 + 20 + 10000 + + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-013/mcdc/heu-met-fast-013.py b/icsbep/openmc/heu-met-fast-013/mcdc/heu-met-fast-013.py new file mode 100644 index 0000000..5b13c71 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-013/mcdc/heu-met-fast-013.py @@ -0,0 +1,117 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041011], + ['U238',0.0040989], + ['C0',0.00039946], + ['Fe54',7.911792e-06], + ['Fe56',0.0001241982144], + ['Fe57',2.8682784e-06], + ['Fe58',3.8171519999999996e-07], + ['W180',1.4808e-08], + ['W182',3.2701e-06], + ['W183',1.7658540000000001e-06], + ['W184',3.780976e-06], + ['W186',3.508262e-06], + ['Cu63',0.00050432478], + ['Cu65',0.00022499521999999998], + ['Ni58',0.00023039265267], + ['Ni60',8.874683733000001e-05], + ['Ni61',3.85776357e-06], + ['Ni62',1.230023835e-05], + ['Ni64',3.13250808e-06]]) +# Material Name: Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00482533975], + ['Fe56',0.0757475147], + ['Fe57',0.0017493404500000002], + ['Fe58',0.0002328051], + ['C0',0.00077554], + ['Si28',0.0003211898606], + ['Si29',1.6309104699999998e-05], + ['Si30',1.0751034699999998e-05], + ['Cr50',2.9190144500000005e-06], + ['Cr52',5.629028809000001e-05], + ['Cr53',6.38286681e-06], + ['Cr54',1.5888306500000002e-06], + ['Mn55',0.00044508]]) +# Material Name: Pure Fe +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Copper +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.75, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.2], radius=7.55, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.2], radius=8.35, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.2], radius=12.0, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.15, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=0.2, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.7, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s14 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.0, bc='vacuum') +s16 = mcdc.surface('cylinder-y', center=[0.0, 0.2], radius=0.6, bc='interface') +s17 = mcdc.surface('plane-z', z=-15.15, bc='vacuum') +s18 = mcdc.surface('plane-z', z=13.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s3 & -s14, fill=mvoid) +c3 = mcdc.cell(+s1 & -s3 & +s14, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s11, fill=mvoid) +c5 = mcdc.cell(+s3 & -s5 & -s10 & +s14, fill=m1) +c6 = mcdc.cell(+s4 & -s6 & +s11 & +s16, fill=m1) +c7 = mcdc.cell(+s5 & -s7 & -s10, fill=m2) +c8 = mcdc.cell(+s6 & -s8 & +s11, fill=m2) +c9 = mcdc.cell(-s2 & +s3 & +s10 & -s11, fill=mvoid) +c10 = mcdc.cell(+s2 & +s10 & -s11 & -s15, fill=m3) +c11 = mcdc.cell(+s7 & -s15 & -s10 & +s12 & +s17, fill=mvoid) +c12 = mcdc.cell(+s8 & +s11 & -s15 & -s18, fill=mvoid) +c13 = mcdc.cell(+s7 & -s9 & -s12 & -s10, fill=m4) +c14 = mcdc.cell(+s9 & -s13 & -s10 & +s17, fill=m3) +c15 = mcdc.cell(+s9 & -s12 & +s13 & -s10 & +s17, fill=mvoid) +c16 = mcdc.cell(+s3 & -s5 & -s10 & -s14, fill=mvoid) +c17 = mcdc.cell(+s4 & -s6 & +s11 & -s16, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-013/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-013/openmc/generate_materials.py new file mode 100644 index 0000000..5bdcb61 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-013/openmc/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2209e-04) +mat.add_nuclide('U235', 4.1011e-02) +mat.add_nuclide('U236', 8.8453e-05) +mat.add_nuclide('U238', 4.0989e-03) +mat.add_element('C', 3.9946e-04) +mat.add_element('Fe', 1.3536e-04) +mat.add_element('W', 1.2340e-05) +mat.add_element('Cu', 7.2932e-04) +mat.add_element('Ni', 3.3843e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Steel" +mat.set_density('sum') +mat.add_element('Fe', 8.2555e-02) +mat.add_element('C', 7.7554e-04) +mat.add_element('Si', 3.4825e-04) +mat.add_element('Cr', 6.7181e-05) +mat.add_element('Mn', 4.4508e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Pure Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Copper" +mat.set_density('sum') +mat.add_element('Cu', 8.2365e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-013/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-013/openmc/geometry.xml new file mode 100644 index 0000000..c58fb74 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-013/openmc/geometry.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-013/openmc/materials.xml b/icsbep/openmc/heu-met-fast-013/openmc/materials.xml new file mode 100644 index 0000000..52dc79d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-013/openmc/materials.xml @@ -0,0 +1,55 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-013/openmc/plots.xml b/icsbep/openmc/heu-met-fast-013/openmc/plots.xml new file mode 100644 index 0000000..e626058 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-013/openmc/plots.xml @@ -0,0 +1,11 @@ + + + + + yz + 0. 0. 0. + 35. 35. + 750 750 + + + diff --git a/icsbep/openmc/heu-met-fast-013/openmc/settings.xml b/icsbep/openmc/heu-met-fast-013/openmc/settings.xml new file mode 100644 index 0000000..fe5799f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-013/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1. -1. -1. 1. 1. 1. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-014/mcdc/heu-met-fast-014.py b/icsbep/openmc/heu-met-fast-014/mcdc/heu-met-fast-014.py new file mode 100644 index 0000000..e5a6ee5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-014/mcdc/heu-met-fast-014.py @@ -0,0 +1,113 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041032], + ['U238',0.004101], + ['C0',0.00039536000000000004], + ['Fe54',7.897764e-06], + ['Fe56',0.0001239780048], + ['Fe57',2.8631928e-06], + ['Fe58',3.810384e-07], + ['W180',1.4911199999999998e-08], + ['W182',3.29289e-06], + ['W183',1.7781606e-06], + ['W184',3.8073264e-06], + ['W186',3.5327117999999993e-06], + ['Cu63',0.0004927006649999999], + ['Cu65',0.000219809335], + ['Ni58',0.00022507584678000002], + ['Ni60',8.669881322e-05], + ['Ni61',3.7687373799999992e-06], + ['Ni62',1.20163839e-05], + ['Ni64',3.06021872e-06]]) +# Material Name: Duralumin +m2 = mcdc.material(nuclides=[ + ['Al27',0.058077], + ['Mg24',0.000815721732], + ['Mg25',0.00010352663999999999], + ['Mg26',0.00011395162799999999], + ['Mn55',0.00018284], + ['Cu63',0.0007834003500000001], + ['Cu65',0.00034949965000000003]]) +# Material Name: Pure Fe +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Depleted Uranium +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.00023832], + ['U238',0.046826]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.64], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.64], radius=8.35, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.64], radius=9.15, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.64], radius=13.0, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.2, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=0.44, bc='interface') +s12 = mcdc.surface('plane-z', z=0.64, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=11.0, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.0, bc='vacuum') +s16 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.75, bc='interface') +s18 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s19 = mcdc.surface('cylinder-y', center=[0.0, 0.64], radius=0.6, bc='interface') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5, bc='interface') +s21 = mcdc.surface('plane-z', z=-16.0, bc='vacuum') +s22 = mcdc.surface('plane-z', z=14.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s10, fill=mvoid) +c2 = mcdc.cell(+s12 & -s2, fill=mvoid) +c3 = mcdc.cell(+s1 & -s3 & -s10 & +s16 & +s18, fill=m1) +c4 = mcdc.cell(+s2 & -s4 & +s12 & +s16 & +s19, fill=m1) +c5 = mcdc.cell(+s3 & -s5 & -s10 & +s17, fill=m4) +c6 = mcdc.cell(+s4 & -s6 & +s12 & +s17, fill=m4) +c7 = mcdc.cell(+s5 & -s7 & -s10, fill=m4) +c8 = mcdc.cell(+s6 & -s8 & +s12 & +s20, fill=m4) +c9 = mcdc.cell(+s10 & -s11 & -s15, fill=mvoid) +c10 = mcdc.cell(+s11 & -s12 & -s15, fill=m3) +c11 = mcdc.cell(+s7 & -s15 & -s10 & +s13 & +s21, fill=mvoid) +c12 = mcdc.cell(+s8 & -s15 & +s12 & -s22, fill=mvoid) +c13 = mcdc.cell(+s7 & -s9 & -s13 & -s10, fill=m2) +c14 = mcdc.cell(+s9 & -s14 & -s10 & +s21, fill=m2) +c15 = mcdc.cell(+s9 & +s14 & -s13 & -s10 & +s21, fill=mvoid) +c16 = mcdc.cell(+s1 & -s3 & -s10 & -s16, fill=mvoid) +c17 = mcdc.cell(+s2 & -s4 & +s12 & -s16, fill=mvoid) +c18 = mcdc.cell(+s3 & -s5 & -s17 & -s10, fill=mvoid) +c19 = mcdc.cell(+s4 & -s6 & +s12 & -s17, fill=mvoid) +c20 = mcdc.cell(+s1 & -s3 & -s10 & +s16 & -s18, fill=mvoid) +c21 = mcdc.cell(+s2 & -s4 & +s12 & +s16 & -s19, fill=mvoid) +c22 = mcdc.cell(+s6 & -s8 & +s12 & -s20, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# eigenvalue = + +# Simulation Parameters diff --git a/icsbep/openmc/heu-met-fast-014/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-014/openmc/generate_materials.py new file mode 100644 index 0000000..934ccf3 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-014/openmc/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2275e-04) +mat.add_nuclide('U235', 4.1032e-02) +mat.add_nuclide('U236', 8.8021e-05) +mat.add_nuclide('U238', 4.1010e-03) +mat.add_element('C', 3.9536e-04) +mat.add_element('Fe', 1.3512e-04) +mat.add_element('W', 1.2426e-05) +mat.add_element('Cu', 7.1251e-04) +mat.add_element('Ni', 3.3062e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Duralumin" +mat.set_density('sum') +mat.add_element('Al', 5.8077e-02) +mat.add_element('Mg', 1.0332e-03) +mat.add_element('Mn', 1.8284e-04) +mat.add_element('Cu', 1.1329e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Pure Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 2.3832e-04) +mat.add_nuclide('U238', 4.6826e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-014/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-014/openmc/geometry.xml new file mode 100644 index 0000000..c7c8267 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-014/openmc/geometry.xml @@ -0,0 +1,57 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-014/openmc/materials.xml b/icsbep/openmc/heu-met-fast-014/openmc/materials.xml new file mode 100644 index 0000000..4f59bdf --- /dev/null +++ b/icsbep/openmc/heu-met-fast-014/openmc/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-014/openmc/plots.xml b/icsbep/openmc/heu-met-fast-014/openmc/plots.xml new file mode 100644 index 0000000..a98b21d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-014/openmc/plots.xml @@ -0,0 +1,11 @@ + + + + + yz + 0. 0. 0. + 35. 35. + 1000 1000 + + + diff --git a/icsbep/openmc/heu-met-fast-014/openmc/settings.xml b/icsbep/openmc/heu-met-fast-014/openmc/settings.xml new file mode 100644 index 0000000..96d1d07 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-014/openmc/settings.xml @@ -0,0 +1,19 @@ + + + + + + + 3000 + 20 + 10000 + + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-015/mcdc/heu-met-fast-015.py b/icsbep/openmc/heu-met-fast-015/mcdc/heu-met-fast-015.py new file mode 100644 index 0000000..e762482 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-015/mcdc/heu-met-fast-015.py @@ -0,0 +1,94 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Bottom HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.045774], + ['U238',0.0013381], + ['C0',0.0001027], + ['Fe54',2.9342484500000004e-06], + ['Fe56',4.6061425540000005e-05], + ['Fe57',1.06375919e-06], + ['Fe58',1.4156682000000002e-07], + ['W180',1.46388e-09], + ['W182',3.232735e-07], + ['W183',1.7456769e-07], + ['W184',3.7377736e-07], + ['W186',3.4681757e-07]]) +# Material Name: Top HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.045708], + ['U238',0.0013404], + ['C0',0.00010256], + ['Fe54',2.93015695e-06], + ['Fe56',4.599719774e-05], + ['Fe57',1.06227589e-06], + ['Fe58',1.4136942e-07], + ['W180',1.46196e-09], + ['W182',3.2284950000000005e-07], + ['W183',1.7433873e-07], + ['W184',3.7328712e-07], + ['W186',3.4636269e-07]]) +# Material Name: Steel Diaphragm and Steel Plate +m3 = mcdc.material(nuclides=[ + ['Fe54',0.00474222385], + ['Fe56',0.07444277282], + ['Fe57',0.00171920827], + ['Fe58',0.00022879505999999998]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.21, bc='interface') +s3 = mcdc.surface('plane-z', z=5.17, bc='interface') +s4 = mcdc.surface('plane-z', z=6.17, bc='interface') +s5 = mcdc.surface('plane-z', z=6.22, bc='interface') +s6 = mcdc.surface('plane-z', z=6.43, bc='interface') +s7 = mcdc.surface('plane-z', z=11.39, bc='vacuum') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.0, bc='vacuum') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.995, bc='interface') +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.8, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.75, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.6, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s5 & -s6 & -s8 & +s9, fill=m3) +c2 = mcdc.cell(+s1 & -s2 & -s10, fill=m3) +c3 = mcdc.cell(+s2 & -s4 & -s9 & +s12, fill=m1) +c4 = mcdc.cell(+s2 & -s3 & -s12, fill=m1) +c5 = mcdc.cell(+s5 & -s7 & -s9 & +s11, fill=m2) +c6 = mcdc.cell(+s1 & -s5 & -s8 & +s9, fill=mvoid) +c7 = mcdc.cell(+s6 & -s7 & -s8 & +s9, fill=mvoid) +c8 = mcdc.cell(+s1 & -s2 & -s9 & +s10, fill=mvoid) +c9 = mcdc.cell(+s4 & -s5 & -s9, fill=mvoid) +c10 = mcdc.cell(+s3 & -s4 & -s12, fill=mvoid) +c11 = mcdc.cell(+s5 & -s7 & -s11, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-0.6,0.6], y=[-0.6,0.6], z=[5.17,6.17], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-015/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-015/openmc/generate_materials.py new file mode 100644 index 0000000..392ef81 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-015/openmc/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Bottom HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.6597e-04) +mat.add_nuclide('U235', 4.5774e-02) +mat.add_nuclide('U238', 1.3381e-03) +mat.add_element('C', 1.0270e-04) +mat.add_element('Fe', 5.0201e-05) +mat.add_element('W', 1.2199e-06) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Top HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.6404e-04) +mat.add_nuclide('U235', 4.5708e-02) +mat.add_nuclide('U238', 1.3404e-03) +mat.add_element('C', 1.0256e-04) +mat.add_element('Fe', 5.0131e-05) +mat.add_element('W', 1.2183e-06) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel Diaphragm and Steel Plate" +mat.set_density('sum') +mat.add_element('Fe', 8.1133e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-015/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-015/openmc/geometry.xml new file mode 100644 index 0000000..85ec614 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-015/openmc/geometry.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-015/openmc/materials.xml b/icsbep/openmc/heu-met-fast-015/openmc/materials.xml new file mode 100644 index 0000000..b460929 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-015/openmc/materials.xml @@ -0,0 +1,42 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-015/openmc/plots.xml b/icsbep/openmc/heu-met-fast-015/openmc/plots.xml new file mode 100644 index 0000000..871c442 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-015/openmc/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 5.5 + 30. 15. + 1000 500 + + + diff --git a/icsbep/openmc/heu-met-fast-015/openmc/settings.xml b/icsbep/openmc/heu-met-fast-015/openmc/settings.xml new file mode 100644 index 0000000..cf74331 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-015/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -.6 -.6 5.17 .6 .6 6.17 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-018/mcdc/heu-met-fast-018_case-2.py b/icsbep/openmc/heu-met-fast-018/mcdc/heu-met-fast-018_case-2.py new file mode 100644 index 0000000..8ebe543 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-018/mcdc/heu-met-fast-018_case-2.py @@ -0,0 +1,54 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.042064], + ['U238',0.0043626], + ['C0',0.0011074], + ['Fe54',1.129254e-05], + ['Fe56',0.000177268728], + ['Fe57',4.093908e-06], + ['Fe58',5.44824e-07], + ['W180',6.455759999999999e-08], + ['W182',1.4256470000000001e-05], + ['W183',7.698493800000001e-06], + ['W184',1.6483707200000002e-05], + ['W186',1.5294771400000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.0, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.154, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-018/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-018/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..a4dc4a5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-018/openmc/case-2/generate_materials.py @@ -0,0 +1,16 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2111e-04) +mat.add_nuclide('U235', 4.2064e-02) +mat.add_nuclide('U238', 4.3626e-03) +mat.add_element('C', 1.1074e-03) +mat.add_element('Fe', 1.9320e-04) +mat.add_element('W', 5.3798e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-018/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-018/openmc/case-2/geometry.xml new file mode 100644 index 0000000..f0dd6d3 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-018/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-018/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-018/openmc/case-2/materials.xml new file mode 100644 index 0000000..a5d79f8 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-018/openmc/case-2/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-018/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-018/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-018/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-019/mcdc/heu-met-fast-019_case-1.py b/icsbep/openmc/heu-met-fast-019/mcdc/heu-met-fast-019_case-1.py new file mode 100644 index 0000000..a72cdb9 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/mcdc/heu-met-fast-019_case-1.py @@ -0,0 +1,162 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU, Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041845], + ['U238',0.0045054], + ['C12',0.0011058], + ['Fe54',1.15842055e-05], + ['Fe56',0.0001818472526], + ['Fe57',4.1996461e-06], + ['Fe58',5.588958e-07], + ['W180',6.501959999999999e-08], + ['W182',1.4358495000000001e-05], + ['W183',7.7535873e-06], + ['W184',1.66016712e-05], + ['W186',1.54042269e-05]]) +# Material Name: HEU, Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.041769], + ['U238',0.0045313], + ['C12',0.0012895], + ['Fe54',1.2736839500000001e-05], + ['Fe56',0.0001999411414], + ['Fe57',4.6175129e-06], + ['Fe58',6.145062e-07], + ['W180',7.943159999999998e-08], + ['W182',1.7541145e-05], + ['W183',9.4722183e-06], + ['W184',2.0281535199999998e-05], + ['W186',1.88186699e-05]]) +# Material Name: HEU, Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.04239], + ['U238',0.0043476], + ['C12',0.0010214], + ['Fe54',1.05052185e-05], + ['Fe56',0.0001649094642], + ['Fe57',3.8084787e-06], + ['Fe58',5.068386e-07], + ['W180',6.5514e-08], + ['W182',1.4467675e-05], + ['W183',7.8125445e-06], + ['W184',1.6727908e-05], + ['W186',1.55213585e-05]]) +# Material Name: HEU, Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.04236], + ['U238',0.0043676], + ['C12',0.0012074], + ['Fe54',1.2843218500000002e-05], + ['Fe56',0.00020161106419999998], + ['Fe57',4.6560787000000004e-06], + ['Fe58',6.196386e-07], + ['W180',7.28148e-08], + ['W182',1.6079935e-05], + ['W183',8.6831649e-06], + ['W184',1.85920456e-05], + ['W186',1.72510397e-05]]) +# Material Name: HEU, Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.042363], + ['U238',0.0043006], + ['C12',0.00083383], + ['Fe54',9.3175145e-06], + ['Fe56',0.0001462650514], + ['Fe57',3.3778979e-06], + ['Fe58',4.4953619999999997e-07], + ['W180',5.0842799999999997e-08], + ['W182',1.1227785e-05], + ['W183',6.0630038999999996e-06], + ['W184',1.2981861600000001e-05], + ['W186',1.20455067e-05]]) +# Material Name: HEU, Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',0.042309], + ['U238',0.0043843], + ['C12',0.0009273600000000001], + ['Fe54',9.326282e-06], + ['Fe56',0.0001464026824], + ['Fe57',3.3810764000000005e-06], + ['Fe58',4.4995919999999994e-07], + ['W180',5.08908e-08], + ['W182',1.1238385000000001e-05], + ['W183',6.0687279e-06], + ['W184',1.29941176e-05], + ['W186',1.20568787e-05]]) +# Material Name: HEU, Layer 7 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',0.042337], + ['U238',0.0043869], + ['C12',0.0013005], + ['Fe54',1.2844972e-05], + ['Fe56',0.0002016385904], + ['Fe57',4.6567144e-06], + ['Fe58',6.197232e-07], + ['W180',7.28232e-08], + ['W182',1.6081790000000002e-05], + ['W183',8.6841666e-06], + ['W184',1.85941904e-05], + ['W186',1.72530298e-05]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m8 = mcdc.material(nuclides=[ + ['C12',0.076716]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.029, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.75, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.6, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +c9 = mcdc.cell(+s8 & -s9, fill=m8) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-019/mcdc/heu-met-fast-019_case-2.py b/icsbep/openmc/heu-met-fast-019/mcdc/heu-met-fast-019_case-2.py new file mode 100644 index 0000000..e30c01b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/mcdc/heu-met-fast-019_case-2.py @@ -0,0 +1,60 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.042256], + ['U238',0.0043799], + ['C0',0.0010894], + ['Fe54',1.11762245e-05], + ['Fe56',0.0001754428234], + ['Fe57',4.0517399e-06], + ['Fe58',5.392122000000001e-07], + ['W180',6.36228e-08], + ['W182',1.4050035000000002e-05], + ['W183',7.587018900000002e-06], + ['W184',1.62450216e-05], + ['W186',1.5073301700000003e-05]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.076716]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.029, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.6, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-019/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..5360c4e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-1/generate_materials.py @@ -0,0 +1,89 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU, Layer 1" +mat.set_density('sum') +mat.add_nuclide('U234', 5.3913e-04) +mat.add_nuclide('U235', 4.1845e-02) +mat.add_nuclide('U238', 4.5054e-03) +mat.add_element('C', 1.1058e-03) +mat.add_element('Fe', 1.9819e-04) +mat.add_element('W', 5.4183e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU, Layer 2" +mat.set_density('sum') +mat.add_nuclide('U234', 5.4361e-04) +mat.add_nuclide('U235', 4.1769e-02) +mat.add_nuclide('U238', 4.5313e-03) +mat.add_element('C', 1.2895e-03) +mat.add_element('Fe', 2.1791e-04) +mat.add_element('W', 6.6193e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "HEU, Layer 3" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1940e-04) +mat.add_nuclide('U235', 4.2390e-02) +mat.add_nuclide('U238', 4.3476e-03) +mat.add_element('C', 1.0214e-03) +mat.add_element('Fe', 1.7973e-04) +mat.add_element('W', 5.4595e-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU, Layer 4" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1956e-04) +mat.add_nuclide('U235', 4.2360e-02) +mat.add_nuclide('U238', 4.3676e-03) +mat.add_element('C', 1.2074e-03) +mat.add_element('Fe', 2.1973e-04) +mat.add_element('W', 6.0679e-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU, Layer 5" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1351e-04) +mat.add_nuclide('U235', 4.2363e-02) +mat.add_nuclide('U238', 4.3006e-03) +mat.add_element('C', 8.3383e-04) +mat.add_element('Fe', 1.5941e-04) +mat.add_element('W', 4.2369e-05) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "HEU, Layer 6" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2352e-04) +mat.add_nuclide('U235', 4.2309e-02) +mat.add_nuclide('U238', 4.3843e-03) +mat.add_element('C', 9.2736e-04) +mat.add_element('Fe', 1.5956e-04) +mat.add_element('W', 4.2409e-05) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "HEU, Layer 7" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2439e-04) +mat.add_nuclide('U235', 4.2337e-02) +mat.add_nuclide('U238', 4.3869e-03) +mat.add_element('C', 1.3005e-03) +mat.add_element('Fe', 2.1976e-04) +mat.add_element('W', 6.0686e-05) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 7.6716e-2) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-019/openmc/case-1/geometry.xml new file mode 100644 index 0000000..d27510d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-1/geometry.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-019/openmc/case-1/materials.xml new file mode 100644 index 0000000..ceb8244 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-1/materials.xml @@ -0,0 +1,120 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-019/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-019/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..4b4c709 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-2/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2315e-04) +mat.add_nuclide('U235', 4.2256e-02) +mat.add_nuclide('U238', 4.3799e-03) +mat.add_element('C', 1.0894e-03) +mat.add_element('Fe', 1.9121e-04) +mat.add_element('W', 5.3019e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 7.6716e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-019/openmc/case-2/geometry.xml new file mode 100644 index 0000000..25d8838 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-019/openmc/case-2/materials.xml new file mode 100644 index 0000000..efd8463 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-2/materials.xml @@ -0,0 +1,24 @@ + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-019/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-019/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-019/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-020/mcdc/heu-met-fast-020_case-2.py b/icsbep/openmc/heu-met-fast-020/mcdc/heu-met-fast-020_case-2.py new file mode 100644 index 0000000..ae8a222 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-020/mcdc/heu-met-fast-020_case-2.py @@ -0,0 +1,59 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.042315], + ['U238',0.0043901], + ['C0',0.0010548], + ['Fe54',1.08874815e-05], + ['Fe56',0.0001709101758], + ['Fe57',3.9470613e-06], + ['Fe58',5.252813999999999e-07], + ['W180',6.2448e-08], + ['W182',1.3790600000000001e-05], + ['W183',7.446924000000001e-06], + ['W184',1.5945056e-05], + ['W186',1.4794972000000003e-05]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['H1',0.077711], + ['C0',0.038856]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.8, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-020/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-020/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..cf45105 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-020/openmc/case-2/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2428e-04) +mat.add_nuclide('U235', 4.2315e-02) +mat.add_nuclide('U238', 4.3901e-03) +mat.add_element('C', 1.0548e-03) +mat.add_element('Fe', 1.8627e-04) +mat.add_element('W', 5.2040e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_nuclide('H1', 7.7711e-02) +mat.add_element('C', 3.8856e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-020/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-020/openmc/case-2/geometry.xml new file mode 100644 index 0000000..385471d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-020/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-020/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-020/openmc/case-2/materials.xml new file mode 100644 index 0000000..ea6e98f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-020/openmc/case-2/materials.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-020/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-020/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-020/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-021/mcdc/heu-met-fast-021_case-2.py b/icsbep/openmc/heu-met-fast-021/mcdc/heu-met-fast-021_case-2.py new file mode 100644 index 0000000..4eb8867 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-021/mcdc/heu-met-fast-021_case-2.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.042023], + ['U238',0.0043613], + ['C0',0.0010919], + ['Fe54',1.1359757500000001e-05], + ['Fe56',0.00017832389900000002], + ['Fe57',4.1182765e-06], + ['Fe58',5.48067e-07], + ['W180',6.606e-08], + ['W182',1.4588250000000002e-05], + ['W183',7.877655000000001e-06], + ['W184',1.686732e-05], + ['W186',1.5650715e-05]]) +# Material Name: Steel reflector 1 +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00464192365], + ['Fe56',0.07286827418], + ['Fe57',0.0016828462300000002], + ['Fe58',0.00022395594], + ['C0',0.0011269], + ['Si28',0.00014816698092000002], + ['Si29',7.523496540000001e-06], + ['Si30',4.95952254e-06], + ['Cr50',1.1310904e-05], + ['Cr52',0.0002181195248], + ['Cr53',2.4733003199999997e-05], + ['Cr54',6.156567999999999e-06], + ['Mn55',0.00032851], + ['Ni58',0.00015700575447], + ['Ni60',6.047833552999999e-05], + ['Ni61',2.6289513699999997e-06], + ['Ni62',8.38224735e-06], + ['Ni64',2.1347112800000003e-06], + ['Cu63',0.000147296415], + ['Cu65',6.571358499999999e-05]]) +# Material Name: Steel reflector 2 +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0046201802500000005], + ['Fe56',0.0725269493], + ['Fe57',0.0016749635500000002], + ['Fe58',0.00022290690000000002], + ['C0',0.0011217], + ['Si28',0.00014747525832000001], + ['Si29',7.488372840000002e-06], + ['Si30',4.93636884e-06], + ['Cr50',1.1257895e-05], + ['Cr52',0.00021709729900000002], + ['Cr53',2.4617091e-05], + ['Cr54',6.127715e-06], + ['Mn55',0.00032697], + ['Ni58',0.00015627052395], + ['Ni60',6.0195126049999996e-05], + ['Ni61',2.6166404499999996e-06], + ['Ni62',8.34299475e-06], + ['Ni64',2.1247148e-06], + ['Cu63',0.000146604915], + ['Cu65',6.5405085e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.89, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.25, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-021/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-021/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..b8b1fa7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-021/openmc/case-2/generate_materials.py @@ -0,0 +1,40 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2087e-04) +mat.add_nuclide('U235', 4.2023e-02) +mat.add_nuclide('U238', 4.3613e-03) +mat.add_element('C', 1.0919e-03) +mat.add_element('Fe', 1.9435e-04) +mat.add_element('W', 5.5050e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Steel reflector 1" +mat.set_density('sum') +mat.add_element('Fe', 7.9417e-02) +mat.add_element('C', 1.1269e-03) +mat.add_element('Si', 1.6065e-04) +mat.add_element('Cr', 2.6032e-04) +mat.add_element('Mn', 3.2851e-04) +mat.add_element('Ni', 2.3063e-04) +mat.add_element('Cu', 2.1301e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel reflector 2" +mat.set_density('sum') +mat.add_element('Fe', 7.9045e-02) +mat.add_element('C', 1.1217e-03) +mat.add_element('Si', 1.5990e-04) +mat.add_element('Cr', 2.5910e-04) +mat.add_element('Mn', 3.2697e-04) +mat.add_element('Ni', 2.2955e-04) +mat.add_element('Cu', 2.1201e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-021/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-021/openmc/case-2/geometry.xml new file mode 100644 index 0000000..3eb4207 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-021/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-021/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-021/openmc/case-2/materials.xml new file mode 100644 index 0000000..13dbe0d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-021/openmc/case-2/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-021/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-021/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-021/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-022/mcdc/heu-met-fast-022_case-2.py b/icsbep/openmc/heu-met-fast-022/mcdc/heu-met-fast-022_case-2.py new file mode 100644 index 0000000..89778a8 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-022/mcdc/heu-met-fast-022_case-2.py @@ -0,0 +1,65 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.042055], + ['U238',0.0043629], + ['C0',0.0010482], + ['Fe54',1.0821433000000001e-05], + ['Fe56',0.0001698733556], + ['Fe57',3.9231166e-06], + ['Fe58',5.220948e-07], + ['W180',6.205559999999999e-08], + ['W182',1.3703944999999999e-05], + ['W183',7.4001303e-06], + ['W184',1.58448632e-05], + ['W186',1.4702005899999999e-05]]) +# Material Name: Duralumin reflector +m2 = mcdc.material(nuclides=[ + ['Al27',0.053934], + ['Fe54',5.769131899999999e-05], + ['Fe56',0.0009056303308], + ['Fe57',2.09149538e-05], + ['Fe58',2.7833964e-06], + ['Cu63',0.00070263315], + ['Cu65',0.00031346685]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.018, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.25, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-022/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-022/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..26a5b2d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-022/openmc/case-2/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2104e-04) +mat.add_nuclide('U235', 4.2055e-02) +mat.add_nuclide('U238', 4.3629e-03) +mat.add_element('C', 1.0482e-03) +mat.add_element('Fe', 1.8514e-04) +mat.add_element('W', 5.1713e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Duralumin reflector" +mat.set_density('sum') +mat.add_element('Al', 5.3934e-02) +mat.add_element('Fe', 9.8702e-04) +mat.add_element('Cu', 1.0161e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-022/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-022/openmc/case-2/geometry.xml new file mode 100644 index 0000000..8600e38 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-022/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-022/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-022/openmc/case-2/materials.xml new file mode 100644 index 0000000..24f122c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-022/openmc/case-2/materials.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-022/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-022/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-022/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-026/mcdc/heu-met-fast-026_c-11.py b/icsbep/openmc/heu-met-fast-026/mcdc/heu-met-fast-026_c-11.py new file mode 100644 index 0000000..a56e698 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-026/mcdc/heu-met-fast-026_c-11.py @@ -0,0 +1,166 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044797], + ['U238',0.0026577]]) +# Material Name: Stainless Steel +m2 = mcdc.material(nuclides=[ + ['C0',0.00031691], + ['Mn55',0.0017320999999999999], + ['Si28',0.0015623707792], + ['Si29',7.93327304e-05], + ['Si30',5.2296490399999995e-05], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Fe54',0.003528042], + ['Fe56',0.0553827144], + ['Fe57',0.0012790284], + ['Fe58',0.00017021519999999997], + ['Ni58',0.0044136977346], + ['Ni60',0.0017001484654], + ['Ni61',7.39042766e-05], + ['Ni62',0.000235639173], + ['Ni64',6.001035040000001e-05]]) +# Material Name: Concrete +m3 = mcdc.material(nuclides=[ + ['H1',0.01486568445768], + ['H2',2.31554232e-06], + ['C0',0.0038144000000000003], + ['O16',0.041503264298999996], + ['O17',1.5735701e-05], + ['Na23',0.000304], + ['Mg24',0.00046344237], + ['Mg25',5.88174e-05], + ['Mg26',6.474023e-05], + ['Al27',0.000735], + ['Si28',0.005567905781599999], + ['Si29',0.0002827223692], + ['Si30',0.0001863718492], + ['Ca40',0.01123352308], + ['Ca42',7.497436e-05], + ['Ca43',1.56438e-05], + ['Ca44',0.00024172568], + ['Ca46',4.6352e-07], + ['Ca48',2.166956e-05], + ['Fe54',1.150296e-05], + ['Fe56',0.00018057187200000002], + ['Fe57',4.170192e-06], + ['Fe58',5.549760000000001e-07]]) +# Material Name: Paraffin +# S(a,b): c_H_in_CH2 (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.082574], + ['C0',0.039699]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=5.742, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, -4.2735], radius=0.254, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 4.2735], radius=0.254, bc='interface') +s7 = mcdc.surface('plane-z', z=-5.3825, bc='interface') +s8 = mcdc.surface('plane-z', z=5.3825, bc='interface') +s18 = mcdc.surface('plane-x', x=-52.906, bc='interface') +s19 = mcdc.surface('plane-x', x=-45.306, bc='interface') +s20 = mcdc.surface('plane-x', x=-30.458, bc='interface') +s21 = mcdc.surface('plane-x', x=-29.95, bc='interface') +s23 = mcdc.surface('plane-x', x=-0.254, bc='interface') +s24 = mcdc.surface('plane-x', x=0.254, bc='interface') +s26 = mcdc.surface('plane-x', x=29.95, bc='interface') +s27 = mcdc.surface('plane-x', x=30.458, bc='interface') +s28 = mcdc.surface('plane-x', x=45.306, bc='interface') +s29 = mcdc.surface('plane-x', x=52.906, bc='interface') +s12 = mcdc.surface('plane-y', y=-52.906, bc='interface') +s13 = mcdc.surface('plane-y', y=-45.306, bc='interface') +s16 = mcdc.surface('plane-y', y=45.306, bc='interface') +s17 = mcdc.surface('plane-y', y=52.906, bc='interface') +s4 = mcdc.surface('plane-z', z=-51.8275, bc='interface') +s5 = mcdc.surface('plane-z', z=-44.2275, bc='interface') +s10 = mcdc.surface('plane-z', z=44.2275, bc='interface') +s11 = mcdc.surface('plane-z', z=51.8275, bc='interface') +s30 = mcdc.surface('plane-x', x=-496.57, bc='vacuum') +s31 = mcdc.surface('plane-x', x=-344.17, bc='interface') +s32 = mcdc.surface('plane-x', x=554.99, bc='interface') +s33 = mcdc.surface('plane-x', x=600.71, bc='vacuum') +s34 = mcdc.surface('plane-y', y=-624.84, bc='vacuum') +s35 = mcdc.surface('plane-y', y=-563.88, bc='interface') +s36 = mcdc.surface('plane-y', y=-502.92, bc='interface') +s37 = mcdc.surface('plane-y', y=428.96, bc='interface') +s38 = mcdc.surface('plane-y', y=581.36, bc='vacuum') +s39 = mcdc.surface('plane-z', z=-265.3725, bc='vacuum') +s40 = mcdc.surface('plane-z', z=-173.9325, bc='interface') +s41 = mcdc.surface('plane-z', z=191.8275, bc='interface') +s42 = mcdc.surface('plane-z', z=905.5675, bc='interface') +s43 = mcdc.surface('plane-z', z=936.0475, bc='vacuum') + +# Material Cell(s) +c10 = mcdc.cell(-s1 & +s2 & +s3 & +s7 & -s8, fill=m1) +c11 = mcdc.cell(-s2 & +s7, fill=m2) +c12 = mcdc.cell(-s3 & +s7, fill=m2) +c13 = mcdc.cell(+s1 & +s7 & -s8, fill=mvoid) +c14 = mcdc.cell(-s7, fill=mvoid) +c15 = mcdc.cell(+s2 & +s3 & +s8, fill=mvoid) +c20 = mcdc.cell(-s1 & +s2 & +s3 & +s7 & -s8, fill=m1) +c21 = mcdc.cell(-s2, fill=m2) +c22 = mcdc.cell(-s3, fill=m2) +c23 = mcdc.cell(+s1 & +s7 & -s8, fill=mvoid) +c24 = mcdc.cell(+s2 & +s3 & -s7, fill=mvoid) +c25 = mcdc.cell(+s2 & +s3 & +s8, fill=mvoid) +c30 = mcdc.cell(-s1 & +s2 & +s3 & +s7 & -s8, fill=m1) +c31 = mcdc.cell(-s2 & -s8, fill=m2) +c32 = mcdc.cell(-s3 & -s8, fill=m2) +c33 = mcdc.cell(+s1 & +s7 & -s8, fill=mvoid) +c34 = mcdc.cell(+s2 & +s3 & -s7, fill=mvoid) +c35 = mcdc.cell(+s8, fill=mvoid) +c40 = mcdc.cell(+s19 & -s20 & +s13 & -s16 & +s4 & -s5, fill=m4) +c41 = mcdc.cell(+s20 & -s21 & +s13 & -s16 & +s4 & -s5, fill=mvoid) +c42 = mcdc.cell(+s21 & -s23 & +s13 & -s16 & +s4 & -s5, fill=m4) +c43 = mcdc.cell(+s23 & -s24 & +s13 & -s16 & +s4 & -s5, fill=mvoid) +c44 = mcdc.cell(+s24 & -s26 & +s13 & -s16 & +s4 & -s5, fill=m4) +c45 = mcdc.cell(+s26 & -s27 & +s13 & -s16 & +s4 & -s5, fill=mvoid) +c46 = mcdc.cell(+s27 & -s28 & +s13 & -s16 & +s4 & -s5, fill=m4) +c47 = mcdc.cell(+s19 & -s20 & +s13 & -s16 & +s10 & -s11, fill=m4) +c48 = mcdc.cell(+s20 & -s21 & +s13 & -s16 & +s10 & -s11, fill=mvoid) +c49 = mcdc.cell(+s21 & -s23 & +s13 & -s16 & +s10 & -s11, fill=m4) +c50 = mcdc.cell(+s23 & -s24 & +s13 & -s16 & +s10 & -s11, fill=mvoid) +c51 = mcdc.cell(+s24 & -s26 & +s13 & -s16 & +s10 & -s11, fill=m4) +c52 = mcdc.cell(+s26 & -s27 & +s13 & -s16 & +s10 & -s11, fill=mvoid) +c53 = mcdc.cell(+s27 & -s28 & +s13 & -s16 & +s10 & -s11, fill=m4) +c54 = mcdc.cell(+s18 & -s29 & +s12 & -s13 & +s4 & -s11, fill=m4) +c55 = mcdc.cell(+s18 & -s29 & +s16 & -s17 & +s4 & -s11, fill=m4) +c56 = mcdc.cell(+s18 & -s19 & +s13 & -s16 & +s4 & -s11, fill=m4) +c57 = mcdc.cell(+s28 & -s29 & +s13 & -s16 & +s4 & -s11, fill=m4) +c80 = mcdc.cell(+s31 & -s32 & +s36 & -s37 & +s40 & -s4, fill=mvoid) +c81 = mcdc.cell(+s31 & -s32 & +s36 & -s12 & +s4 & -s11, fill=mvoid) +c82 = mcdc.cell(+s31 & -s18 & +s12 & -s17 & +s4 & -s11, fill=mvoid) +c83 = mcdc.cell(+s29 & -s32 & +s12 & -s17 & +s4 & -s11, fill=mvoid) +c84 = mcdc.cell(+s31 & -s32 & +s17 & -s37 & +s4 & -s11, fill=mvoid) +c85 = mcdc.cell(+s31 & -s32 & +s36 & -s37 & +s11 & -s41, fill=mvoid) +c86 = mcdc.cell(+s31 & -s32 & +s35 & -s37 & +s41 & -s42, fill=mvoid) +c87 = mcdc.cell(+s30 & -s33 & +s34 & -s38 & +s39 & -s40, fill=m3) +c88 = mcdc.cell(+s30 & -s33 & +s34 & -s36 & +s40 & -s41, fill=m3) +c89 = mcdc.cell(+s30 & -s33 & +s34 & -s35 & +s41 & -s42, fill=m3) +c90 = mcdc.cell(+s30 & -s31 & +s35 & -s36 & +s41 & -s42, fill=m3) +c91 = mcdc.cell(+s32 & -s33 & +s35 & -s36 & +s41 & -s42, fill=m3) +c92 = mcdc.cell(+s30 & -s31 & +s36 & -s37 & +s40 & -s42, fill=m3) +c93 = mcdc.cell(+s32 & -s33 & +s36 & -s37 & +s40 & -s42, fill=m3) +c94 = mcdc.cell(+s30 & -s33 & +s37 & -s38 & +s40 & -s42, fill=m3) +c95 = mcdc.cell(+s30 & -s33 & +s34 & -s38 & +s42 & -s43, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 101 +Lattice101 = mcdc.lattice(x=[-45.306, 30.204, 3], y=[-45.306, 30.204, 3], z=[-44.2275, 29.485, 3], \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-026/openmc/c-11/generate_materials.py b/icsbep/openmc/heu-met-fast-026/openmc/c-11/generate_materials.py new file mode 100644 index 0000000..cb94557 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-026/openmc/c-11/generate_materials.py @@ -0,0 +1,47 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8271e-04) +mat.add_nuclide('U235', 4.4797e-02) +mat.add_nuclide('U236', 9.5723e-05) +mat.add_nuclide('U238', 2.6577e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless Steel" +mat.set_density('sum') +mat.add_element('C', 3.1691e-04) +mat.add_element('Mn', 1.7321e-03) +mat.add_element('Si', 1.6940e-03) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Fe', 6.0360e-02) +mat.add_element('Ni', 6.4834e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_element('H', 1.4868e-02) +mat.add_element('C', 3.8144e-03) +mat.add_element('O', 4.1519e-02) +mat.add_element('Na', 3.0400e-04) +mat.add_element('Mg', 5.8700e-04) +mat.add_element('Al', 7.3500e-04) +mat.add_element('Si', 6.0370e-03) +mat.add_element('Ca', 1.1588e-02) +mat.add_element('Fe', 1.9680e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Paraffin" +mat.set_density('sum') +mat.add_nuclide('H1', 8.2574e-02) +mat.add_element('C', 3.9699e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-026/openmc/c-11/geometry.xml b/icsbep/openmc/heu-met-fast-026/openmc/c-11/geometry.xml new file mode 100644 index 0000000..da54f8b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-026/openmc/c-11/geometry.xml @@ -0,0 +1,138 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 3 3 3 + -45.306 -45.306 -44.2275 + 30.204 30.204 29.485 + + 1 1 1 1 1 1 1 1 1 + 2 2 2 2 2 2 2 2 2 + 3 3 3 3 3 3 3 3 3 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-026/openmc/c-11/materials.xml b/icsbep/openmc/heu-met-fast-026/openmc/c-11/materials.xml new file mode 100644 index 0000000..5c13854 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-026/openmc/c-11/materials.xml @@ -0,0 +1,63 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-026/openmc/c-11/plots.xml b/icsbep/openmc/heu-met-fast-026/openmc/c-11/plots.xml new file mode 100644 index 0000000..d6a954d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-026/openmc/c-11/plots.xml @@ -0,0 +1,34 @@ + + + + + + + yz + 0. 0. 0. + 150. 150. + 1000 1000 + + + + xy + 0. 0. 0. + 150. 150. + 1000 1000 + + + + xz + 0. 0. 0. + 150. 150. + 1000 1000 + + + diff --git a/icsbep/openmc/heu-met-fast-026/openmc/c-11/settings.xml b/icsbep/openmc/heu-met-fast-026/openmc/c-11/settings.xml new file mode 100644 index 0000000..fecb514 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-026/openmc/c-11/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-027/mcdc/heu-met-fast-027.py b/icsbep/openmc/heu-met-fast-027/mcdc/heu-met-fast-027.py new file mode 100644 index 0000000..bb0f1a7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-027/mcdc/heu-met-fast-027.py @@ -0,0 +1,202 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU, Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041828], + ['U238',0.0042699], + ['C0',0.0007319], + ['Fe54',6.9006070000000005e-06], + ['Fe56',0.00010832477240000001], + ['Fe57',2.5016914000000003e-06], + ['Fe58',3.329292e-07], + ['W180',4.30344e-08], + ['W182',9.503430000000002e-06], + ['W183',5.131852200000001e-06], + ['W184',1.09881168e-05], + ['W186',1.0195566600000001e-05]]) +# Material Name: HEU, Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.041658], + ['U238',0.0041803], + ['C0',0.0014583], + ['Fe54',1.3749193500000001e-05], + ['Fe56',0.00021583293420000002], + ['Fe57',4.9845237e-06], + ['Fe58',6.633486000000001e-07], + ['W180',8.574599999999999e-08], + ['W182',1.8935575e-05], + ['W183',1.02252105e-05], + ['W184',2.1893812e-05], + ['W186',2.0314656499999998e-05]]) +# Material Name: HEU, Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.041312], + ['U238',0.0044603], + ['C0',0.0012746], + ['Fe54',1.2588961e-05], + ['Fe56',0.0001976197652], + ['Fe57',4.5639022e-06], + ['Fe58',6.073716e-07], + ['W180',7.13724e-08], + ['W182',1.5761405e-05], + ['W183',8.5111587e-06], + ['W184',1.82237528e-05], + ['W186',1.69093111e-05]]) +# Material Name: HEU, Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.041823], + ['U238',0.0045031], + ['C0',0.0011052], + ['Fe54',1.15783605e-05], + ['Fe56',0.0001817554986], + ['Fe57',4.1975271e-06], + ['Fe58',5.586138e-07], + ['W180',6.498479999999999e-08], + ['W182',1.4350810000000002e-05], + ['W183',7.7494374e-06], + ['W184',1.65927856e-05], + ['W186',1.53959822e-05]]) +# Material Name: HEU, Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.041769], + ['U238',0.0045313], + ['C0',0.0012895], + ['Fe54',1.2736839500000001e-05], + ['Fe56',0.0001999411414], + ['Fe57',4.6175129e-06], + ['Fe58',6.145062e-07], + ['W180',7.943159999999998e-08], + ['W182',1.7541145e-05], + ['W183',9.4722183e-06], + ['W184',2.0281535199999998e-05], + ['W186',1.88186699e-05]]) +# Material Name: HEU, Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',0.04239], + ['U238',0.0043476], + ['C0',0.0010214], + ['Fe54',1.05052185e-05], + ['Fe56',0.0001649094642], + ['Fe57',3.8084787e-06], + ['Fe58',5.068386e-07], + ['W180',6.5514e-08], + ['W182',1.4467675e-05], + ['W183',7.8125445e-06], + ['W184',1.6727908e-05], + ['W186',1.55213585e-05]]) +# Material Name: HEU, Layer 7 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',0.04236], + ['U238',0.0043676], + ['C0',0.0012074], + ['Fe54',1.2843218500000002e-05], + ['Fe56',0.00020161106419999998], + ['Fe57',4.6560787000000004e-06], + ['Fe58',6.196386e-07], + ['W180',7.28148e-08], + ['W182',1.6079935e-05], + ['W183',8.6831649e-06], + ['W184',1.85920456e-05], + ['W186',1.72510397e-05]]) +# Material Name: HEU, Layer 8 +# Depletable +m8 = mcdc.material(nuclides=[ + ['U235',0.042363], + ['U238',0.0043006], + ['C0',0.00083383], + ['Fe54',9.3175145e-06], + ['Fe56',0.0001462650514], + ['Fe57',3.3778979e-06], + ['Fe58',4.4953619999999997e-07], + ['W180',5.0842799999999997e-08], + ['W182',1.1227785e-05], + ['W183',6.0630038999999996e-06], + ['W184',1.2981861600000001e-05], + ['W186',1.20455067e-05]]) +# Material Name: HEU, Layer 9 +# Depletable +m9 = mcdc.material(nuclides=[ + ['U235',0.042309], + ['U238',0.0043843], + ['C0',0.0009273600000000001], + ['Fe54',9.326282e-06], + ['Fe56',0.0001464026824], + ['Fe57',3.3810764000000005e-06], + ['Fe58',4.4995919999999994e-07], + ['W180',5.08908e-08], + ['W182',1.1238385000000001e-05], + ['W183',6.0687279e-06], + ['W184',1.29941176e-05], + ['W186',1.20568787e-05]]) +# Material Name: Lead +m10 = mcdc.material(nuclides=[ + ['Pb204',0.000459732], + ['Pb206',0.007913957999999999], + ['Pb207',0.007257198], + ['Pb208',0.017207112], + ['Fe54',1.0754215500000001e-06], + ['Fe56',1.6881818460000003e-05], + ['Fe57',3.8987481e-07], + ['Fe58',5.188518e-08]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.019, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.75, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s10 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s11 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.6, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +c9 = mcdc.cell(+s8 & -s9, fill=m8) +c10 = mcdc.cell(+s9 & -s10, fill=m9) +c11 = mcdc.cell(+s10 & -s11, fill=m10) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-027/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-027/openmc/generate_materials.py new file mode 100644 index 0000000..3bf6207 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-027/openmc/generate_materials.py @@ -0,0 +1,111 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU, Layer 1" +mat.set_density('sum') +mat.add_nuclide('U234', 5.0708e-04) +mat.add_nuclide('U235', 4.1828e-02) +mat.add_nuclide('U238', 4.2699e-03) +mat.add_element('C', 7.3190e-04) +mat.add_element('Fe', 1.1806e-04) +mat.add_element('W', 3.5862e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU, Layer 2" +mat.set_density('sum') +mat.add_nuclide('U234', 5.0050e-04) +mat.add_nuclide('U235', 4.1658e-02) +mat.add_nuclide('U238', 4.1803e-03) +mat.add_element('C', 1.4583e-03) +mat.add_element('Fe', 2.3523e-04) +mat.add_element('W', 7.1455e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "HEU, Layer 3" +mat.set_density('sum') +mat.add_nuclide('U234', 5.3263e-04) +mat.add_nuclide('U235', 4.1312e-02) +mat.add_nuclide('U238', 4.4603e-03) +mat.add_element('C', 1.2746e-03) +mat.add_element('Fe', 2.1538e-04) +mat.add_element('W', 5.9477e-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU, Layer 4" +mat.set_density('sum') +mat.add_nuclide('U234', 5.3885e-04) +mat.add_nuclide('U235', 4.1823e-02) +mat.add_nuclide('U238', 4.5031e-03) +mat.add_element('C', 1.1052e-03) +mat.add_element('Fe', 1.9809e-04) +mat.add_element('W', 5.4154e-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU, Layer 5" +mat.set_density('sum') +mat.add_nuclide('U234', 5.4361e-04) +mat.add_nuclide('U235', 4.1769e-02) +mat.add_nuclide('U238', 4.5313e-03) +mat.add_element('C', 1.2895e-03) +mat.add_element('Fe', 2.1791e-04) +mat.add_element('W', 6.6193e-05) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "HEU, Layer 6" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1940e-04) +mat.add_nuclide('U235', 4.2390e-02) +mat.add_nuclide('U238', 4.3476e-03) +mat.add_element('C', 1.0214e-03) +mat.add_element('Fe', 1.7973e-04) +mat.add_element('W', 5.4595e-05) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "HEU, Layer 7" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1956e-04) +mat.add_nuclide('U235', 4.2360e-02) +mat.add_nuclide('U238', 4.3676e-03) +mat.add_element('C', 1.2074e-03) +mat.add_element('Fe', 2.1973e-04) +mat.add_element('W', 6.0679e-05) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "HEU, Layer 8" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1351e-04) +mat.add_nuclide('U235', 4.2363e-02) +mat.add_nuclide('U238', 4.3006e-03) +mat.add_element('C', 8.3383e-04) +mat.add_element('Fe', 1.5941e-04) +mat.add_element('W', 4.2369e-05) +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "HEU, Layer 9" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2352e-04) +mat.add_nuclide('U235', 4.2309e-02) +mat.add_nuclide('U238', 4.3843e-03) +mat.add_element('C', 9.2736e-04) +mat.add_element('Fe', 1.5956e-04) +mat.add_element('W', 4.2409e-05) +mats.append(mat) + +mat = openmc.Material(10) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2838e-02) +mat.add_element('Fe', 1.8399e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-027/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-027/openmc/geometry.xml new file mode 100644 index 0000000..2c58e15 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-027/openmc/geometry.xml @@ -0,0 +1,35 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-027/openmc/materials.xml b/icsbep/openmc/heu-met-fast-027/openmc/materials.xml new file mode 100644 index 0000000..56078bd --- /dev/null +++ b/icsbep/openmc/heu-met-fast-027/openmc/materials.xml @@ -0,0 +1,158 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-027/openmc/settings.xml b/icsbep/openmc/heu-met-fast-027/openmc/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-027/openmc/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-028/mcdc/heu-met-fast-028.py b/icsbep/openmc/heu-met-fast-028/mcdc/heu-met-fast-028.py new file mode 100644 index 0000000..8cc594f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-028/mcdc/heu-met-fast-028.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044482], + ['U238',0.0027038]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.0003461], + ['U238',0.047721]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.1156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=24.1242, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-028/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-028/openmc/geometry.xml new file mode 100644 index 0000000..efb727c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-028/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-028/openmc/materials.xml b/icsbep/openmc/heu-met-fast-028/openmc/materials.xml new file mode 100644 index 0000000..7ba3174 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-028/openmc/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-028/openmc/settings.xml b/icsbep/openmc/heu-met-fast-028/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-028/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-029/mcdc/heu-met-fast-029.py b/icsbep/openmc/heu-met-fast-029/mcdc/heu-met-fast-029.py new file mode 100644 index 0000000..6d6fe77 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-029/mcdc/heu-met-fast-029.py @@ -0,0 +1,190 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU, Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.041441], + ['U238',0.0042953], + ['Cu63',0.000511246695], + ['Cu65',0.000228083305], + ['C0',0.00054396], + ['Ni58',0.0003642794919], + ['Ni60',0.0001403198081], + ['Ni61',6.0996049e-06], + ['Ni62',1.9448209500000004e-05], + ['Ni64',4.952885600000001e-06]]) +# Material Name: HEU, Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.041478], + ['U238',0.004239], + ['Cu63',0.000517345725], + ['Cu65',0.000230804275], + ['C0',0.00054378], + ['Ni58',0.00040539113180999994], + ['Ni60',0.00015615593818999997], + ['Ni61',6.78799051e-06], + ['Ni62',2.1643084049999998e-05], + ['Ni64',5.51185544e-06]]) +# Material Name: HEU, Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.040925], + ['U238',0.0042922], + ['Cu63',0.00064132476], + ['Cu65',0.00028611524], + ['C0',0.00053785], + ['Ni58',0.00045987307487999995], + ['Ni60',0.00017714228512], + ['Ni61',7.70025248e-06], + ['Ni62',2.45517744e-05], + ['Ni64',6.252613119999999e-06]]) +# Material Name: HEU, Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.041135], + ['U238',0.0042744], + ['Cu63',0.00059605917], + ['Cu65',0.00026592083], + ['C0',0.00054074], + ['Ni58',0.00029671316865], + ['Ni60',0.00011429338134999998], + ['Ni61',4.968254149999999e-06], + ['Ni62',1.584096825e-05], + ['Ni64',4.0342276000000004e-06]]) +# Material Name: HEU, Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.041062], + ['U238',0.0042174], + ['Cu63',0.0005793179550000001], + ['Cu65',0.00025845204500000004], + ['C0',0.00044891], + ['Ni58',0.00033665388588], + ['Ni60',0.00012967847412], + ['Ni61',5.63703348e-06], + ['Ni62',1.7973329400000002e-05], + ['Ni64',4.57727712e-06]]) +# Material Name: HEU, Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',0.041306], + ['U238',0.0042137], + ['Cu63',0.0005561872799999999], + ['Cu65',0.00024813271999999997], + ['C0',0.00036114], + ['Ni58',0.00037831694867999997], + ['Ni60',0.00014572701132], + ['Ni61',6.3346522799999985e-06], + ['Ni62',2.0197643400000002e-05], + ['Ni64',5.14374432e-06]]) +# Material Name: HEU, Layer 7 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',0.041191], + ['U238',0.0041791], + ['Cu63',0.00043980783000000006], + ['Cu65',0.00019621217000000005], + ['C0',0.00035973], + ['Ni58',0.00024106030289999998], + ['Ni60',9.285599709999998e-05], + ['Ni61',4.036385899999999e-06], + ['Ni62',1.28697645e-05], + ['Ni64',3.2775496e-06]]) +# Material Name: Depleted uranium, Layer 1 +# Depletable +m8 = mcdc.material(nuclides=[ + ['U235',0.00021044], + ['U238',0.04678], + ['C0',0.0029015], + ['Fe54',2.2354787e-05], + ['Fe56',0.0003509223484], + ['Fe57',8.1043274e-06], + ['Fe58',1.0785372e-06]]) +# Material Name: Depleted uranium, Layer 2 +# Depletable +m9 = mcdc.material(nuclides=[ + ['U235',0.00021047], + ['U238',0.046786], + ['C0',0.0029018], + ['Fe54',2.23577095e-05], + ['Fe56',0.00035096822540000005], + ['Fe57',8.1053869e-06], + ['Fe58',1.0786782e-06]]) +# Material Name: Depleted uranium, Layer 3 +# Depletable +m10 = mcdc.material(nuclides=[ + ['U235',0.00021912], + ['U238',0.045586], + ['C0',0.0028282], + ['Fe54',2.17907445e-05], + ['Fe56',0.0003420680874], + ['Fe57',7.8998439e-06], + ['Fe58',1.0513242000000001e-06]]) +# Material Name: Depleted uranium, Layer 4 +# Depletable +m11 = mcdc.material(nuclides=[ + ['U235',0.00021059], + ['U238',0.045767], + ['C0',0.0028389], + ['Fe54',2.1873159e-05], + ['Fe56',0.0003433618188], + ['Fe57',7.9297218e-06], + ['Fe58',1.0553003999999998e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.91, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.01, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.75, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s10 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s11 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s12 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.25, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +c9 = mcdc.cell(+s8 & -s9, fill=m8) +c10 = mcdc.cell(+s9 & -s10, fill=m9) +c11 = mcdc.cell(+s10 & -s11, fill=m10) +c12 = mcdc.cell(+s11 & -s12, fill=m11) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-029/openmc/generate_materials.py b/icsbep/openmc/heu-met-fast-029/openmc/generate_materials.py new file mode 100644 index 0000000..b61fca5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-029/openmc/generate_materials.py @@ -0,0 +1,118 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU, Layer 1" +mat.set_density('sum') +mat.add_nuclide('U234', 4.6992e-04) +mat.add_nuclide('U235', 4.1441e-02) +mat.add_nuclide('U238', 4.2953e-03) +mat.add_element('Cu', 7.3933e-04) +mat.add_element('C', 5.4396e-04) +mat.add_element('Ni', 5.3510e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU, Layer 2" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7441e-04) +mat.add_nuclide('U235', 4.1478e-02) +mat.add_nuclide('U238', 4.2390e-03) +mat.add_element('Cu', 7.4815e-04) +mat.add_element('C', 5.4378e-04) +mat.add_element('Ni', 5.9549e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "HEU, Layer 3" +mat.set_density('sum') +mat.add_nuclide('U234', 4.6924e-04) +mat.add_nuclide('U235', 4.0925e-02) +mat.add_nuclide('U238', 4.2922e-03) +mat.add_element('Cu', 9.2744e-04) +mat.add_element('C', 5.3785e-04) +mat.add_element('Ni', 6.7552e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU, Layer 4" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2726e-04) +mat.add_nuclide('U235', 4.1135e-02) +mat.add_nuclide('U238', 4.2744e-03) +mat.add_element('Cu', 8.6198e-04) +mat.add_element('C', 5.4074e-04) +mat.add_element('Ni', 4.3585e-04) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU, Layer 5" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8840e-04) +mat.add_nuclide('U235', 4.1062e-02) +mat.add_nuclide('U238', 4.2174e-03) +mat.add_element('Cu', 8.3777e-04) +mat.add_element('C', 4.4891e-04) +mat.add_element('Ni', 4.9452e-04) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "HEU, Layer 6" +mat.set_density('sum') +mat.add_nuclide('U234', 5.0504e-04) +mat.add_nuclide('U235', 4.1306e-02) +mat.add_nuclide('U238', 4.2137e-03) +mat.add_element('Cu', 8.0432e-04) +mat.add_element('C', 3.6114e-04) +mat.add_element('Ni', 5.5572e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "HEU, Layer 7" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8000e-04) +mat.add_nuclide('U235', 4.1191e-02) +mat.add_nuclide('U238', 4.1791e-03) +mat.add_element('Cu', 6.3602e-04) +mat.add_element('C', 3.5973e-04) +mat.add_element('Ni', 3.5410e-04) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Depleted uranium, Layer 1" +mat.set_density('sum') +mat.add_nuclide('U235', 2.1044e-04) +mat.add_nuclide('U238', 4.6780e-02) +mat.add_element('C', 2.9015e-03) +mat.add_element('Fe', 3.8246e-04) +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "Depleted uranium, Layer 2" +mat.set_density('sum') +mat.add_nuclide('U235', 2.1047e-04) +mat.add_nuclide('U238', 4.6786e-02) +mat.add_element('C', 2.9018e-03) +mat.add_element('Fe', 3.8251e-04) +mats.append(mat) + +mat = openmc.Material(10) +mat.name = "Depleted uranium, Layer 3" +mat.set_density('sum') +mat.add_nuclide('U235', 2.1912e-04) +mat.add_nuclide('U238', 4.5586e-02) +mat.add_element('C', 2.8282e-03) +mat.add_element('Fe', 3.7281e-04) +mats.append(mat) + +mat = openmc.Material(11) +mat.name = "Depleted uranium, Layer 4" +mat.set_density('sum') +mat.add_nuclide('U235', 2.1059e-04) +mat.add_nuclide('U238', 4.5767e-02) +mat.add_element('C', 2.8389e-03) +mat.add_element('Fe', 3.7422e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-029/openmc/geometry.xml b/icsbep/openmc/heu-met-fast-029/openmc/geometry.xml new file mode 100644 index 0000000..dafd3bd --- /dev/null +++ b/icsbep/openmc/heu-met-fast-029/openmc/geometry.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-029/openmc/materials.xml b/icsbep/openmc/heu-met-fast-029/openmc/materials.xml new file mode 100644 index 0000000..e43994c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-029/openmc/materials.xml @@ -0,0 +1,141 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-029/openmc/settings.xml b/icsbep/openmc/heu-met-fast-029/openmc/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-029/openmc/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-1.py b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-1.py new file mode 100644 index 0000000..3e0637a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-1.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044965], + ['U238',0.0024019]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.0003461], + ['U238',0.047721]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.32598, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.30818, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-2.py b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-2.py new file mode 100644 index 0000000..5e28d91 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-2.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.045109], + ['U238',0.0024096]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.0003461], + ['U238',0.047721]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.38531, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.32611, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-3.py b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-3.py new file mode 100644 index 0000000..7577b96 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-3.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.04496], + ['U238',0.0023568]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034009], + ['U238',0.046892]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.97659, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.40127, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-4.py b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-4.py new file mode 100644 index 0000000..e23d293 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/mcdc/heu-met-fast-032_case-4.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.044994], + ['U238',0.0023984]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.0003461], + ['U238',0.047721]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.7552, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.49002, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-1/geometry.xml new file mode 100644 index 0000000..f55306d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-1/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-1/materials.xml new file mode 100644 index 0000000..593f022 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-1/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-2/geometry.xml new file mode 100644 index 0000000..a8f3055 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-2/materials.xml new file mode 100644 index 0000000..3fd3dbf --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-2/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-3/geometry.xml new file mode 100644 index 0000000..480102b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-3/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-3/materials.xml new file mode 100644 index 0000000..20e8964 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-3/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-3/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-4/geometry.xml new file mode 100644 index 0000000..32c45f7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-4/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-4/materials.xml new file mode 100644 index 0000000..e83bec5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-4/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-032/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-fast-032/openmc/case-4/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-032/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-1.py b/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-1.py new file mode 100644 index 0000000..c132c21 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-1.py @@ -0,0 +1,176 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.045694], + ['U238',0.001335], + ['C0',7.456e-05], + ['Fe54',1.054438e-06], + ['Fe56',1.65524216e-05], + ['Fe57',3.822676e-07], + ['Fe58',5.08728e-08], + ['W180',1.095984e-09], + ['W182',2.420298e-07], + ['W183',1.30696092e-07], + ['W184',2.79841248e-07], + ['W186',2.59656876e-07]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.03929], + ['H1',0.078579]]) +# Material Name: Titanium +m3 = mcdc.material(nuclides=[ + ['Ti46',0.00467214], + ['Ti47',0.0042134208], + ['Ti48',0.0417491104], + ['Ti49',0.0030637912000000002], + ['Ti50',0.0029335376], + ['Al27',0.0010151]]) +# Material Name: Aluminium +m4 = mcdc.material(nuclides=[ + ['Al27',0.059154], + ['Mn55',0.00038519], + ['Si28',0.000160359744616], + ['Si29',8.142610292e-06], + ['Si30',5.367645092e-06], + ['Fe54',5.963069000000001e-06], + ['Fe56',9.36074308e-05], + ['Fe57',2.1618038e-06], + ['Fe58',2.8769640000000003e-07]]) +# Material Name: Steel +m5 = mcdc.material(nuclides=[ + ['Fe54',0.00484006915], + ['Fe56',0.07597873478], + ['Fe57',0.0017546803300000002], + ['Fe58',0.00023351574000000003], + ['C0',0.00040815], + ['Si28',0.000413954472744], + ['Si29',2.1019427028e-05], + ['Si30',1.3856100228e-05], + ['Mn55',0.00042492], + ['Cr50',2.9261402500000003e-06], + ['Cr52',5.642770205e-05], + ['Cr53',6.398448449999999e-06], + ['Cr54',1.5927092500000001e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-21.24, bc='vacuum') +s2 = mcdc.surface('plane-z', z=-20.75, bc='interface') +s3 = mcdc.surface('plane-z', z=-18.78, bc='interface') +s4 = mcdc.surface('plane-z', z=-18.29, bc='interface') +s5 = mcdc.surface('plane-z', z=-16.3, bc='interface') +s6 = mcdc.surface('plane-z', z=-15.81, bc='interface') +s7 = mcdc.surface('plane-z', z=-13.84, bc='interface') +s8 = mcdc.surface('plane-z', z=-13.35, bc='interface') +s9 = mcdc.surface('plane-z', z=-11.36, bc='interface') +s10 = mcdc.surface('plane-z', z=-10.87, bc='interface') +s11 = mcdc.surface('plane-z', z=-8.9, bc='interface') +s12 = mcdc.surface('plane-z', z=-8.41, bc='interface') +s13 = mcdc.surface('plane-z', z=-6.42, bc='interface') +s14 = mcdc.surface('plane-z', z=-5.93, bc='interface') +s15 = mcdc.surface('plane-z', z=-3.96, bc='interface') +s16 = mcdc.surface('plane-z', z=-3.47, bc='interface') +s17 = mcdc.surface('plane-z', z=-1.48, bc='interface') +s18 = mcdc.surface('plane-z', z=-0.99, bc='interface') +s19 = mcdc.surface('plane-z', z=0.0, bc='interface') +s20 = mcdc.surface('plane-z', z=0.62, bc='interface') +s21 = mcdc.surface('plane-z', z=0.82, bc='interface') +s22 = mcdc.surface('plane-z', z=1.42, bc='interface') +s23 = mcdc.surface('plane-z', z=1.6, bc='interface') +s24 = mcdc.surface('plane-z', z=2.09, bc='interface') +s25 = mcdc.surface('plane-z', z=4.08, bc='interface') +s26 = mcdc.surface('plane-z', z=4.57, bc='interface') +s27 = mcdc.surface('plane-z', z=6.54, bc='interface') +s28 = mcdc.surface('plane-z', z=7.03, bc='interface') +s29 = mcdc.surface('plane-z', z=9.02, bc='interface') +s30 = mcdc.surface('plane-z', z=9.51, bc='interface') +s31 = mcdc.surface('plane-z', z=11.48, bc='interface') +s32 = mcdc.surface('plane-z', z=11.97, bc='interface') +s33 = mcdc.surface('plane-z', z=13.96, bc='interface') +s34 = mcdc.surface('plane-z', z=14.45, bc='interface') +s35 = mcdc.surface('plane-z', z=16.42, bc='interface') +s36 = mcdc.surface('plane-z', z=16.91, bc='interface') +s37 = mcdc.surface('plane-z', z=18.9, bc='interface') +s38 = mcdc.surface('plane-z', z=19.39, bc='interface') +s39 = mcdc.surface('plane-z', z=21.36, bc='interface') +s40 = mcdc.surface('plane-z', z=21.85, bc='vacuum') +s50 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.6, bc='interface') +s51 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.995, bc='interface') +s52 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.0, bc='interface') +s53 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s51, fill=m3) +c2 = mcdc.cell(+s2 & -s3 & -s51, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s51, fill=m3) +c4 = mcdc.cell(+s4 & -s5 & -s51, fill=m1) +c5 = mcdc.cell(+s5 & -s6 & -s51, fill=m3) +c6 = mcdc.cell(+s6 & -s7 & -s51, fill=m2) +c7 = mcdc.cell(+s7 & -s8 & -s51, fill=m3) +c8 = mcdc.cell(+s8 & -s9 & -s51, fill=m1) +c9 = mcdc.cell(+s9 & -s10 & -s51, fill=m3) +c10 = mcdc.cell(+s10 & -s11 & -s51, fill=m2) +c11 = mcdc.cell(+s11 & -s12 & -s51, fill=m3) +c12 = mcdc.cell(+s12 & -s13 & -s51, fill=m1) +c13 = mcdc.cell(+s13 & -s14 & -s51, fill=m3) +c14 = mcdc.cell(+s14 & -s15 & -s51, fill=m2) +c15 = mcdc.cell(+s15 & -s16 & -s51, fill=m3) +c16 = mcdc.cell(+s16 & -s17 & -s51, fill=m1) +c17 = mcdc.cell(+s17 & -s18 & -s51, fill=m3) +c18 = mcdc.cell(+s18 & -s19 & +s50 & -s51, fill=m2) +c19 = mcdc.cell(+s18 & -s19 & -s50, fill=mvoid) +c20 = mcdc.cell(+s19 & -s20 & -s51, fill=mvoid) +c21 = mcdc.cell(+s20 & -s23 & -s51, fill=m2) +c22 = mcdc.cell(+s23 & -s24 & -s51, fill=m3) +c23 = mcdc.cell(+s24 & -s25 & -s51, fill=m1) +c24 = mcdc.cell(+s25 & -s26 & -s51, fill=m3) +c25 = mcdc.cell(+s26 & -s27 & -s51, fill=m2) +c26 = mcdc.cell(+s27 & -s28 & -s51, fill=m3) +c27 = mcdc.cell(+s28 & -s29 & -s51, fill=m1) +c28 = mcdc.cell(+s29 & -s30 & -s51, fill=m3) +c29 = mcdc.cell(+s30 & -s31 & -s51, fill=m2) +c30 = mcdc.cell(+s31 & -s32 & -s51, fill=m3) +c31 = mcdc.cell(+s32 & -s33 & -s51, fill=m1) +c32 = mcdc.cell(+s33 & -s34 & -s51, fill=m3) +c33 = mcdc.cell(+s34 & -s35 & -s51, fill=m2) +c34 = mcdc.cell(+s35 & -s36 & -s51, fill=m3) +c35 = mcdc.cell(+s36 & -s37 & -s51, fill=m1) +c36 = mcdc.cell(+s37 & -s38 & -s51, fill=m3) +c37 = mcdc.cell(+s38 & -s39 & -s51, fill=m2) +c38 = mcdc.cell(+s39 & -s40 & -s51, fill=m3) +c39 = mcdc.cell(+s20 & -s21 & +s51 & -s52, fill=m5) +c40 = mcdc.cell(+s20 & -s22 & +s52 & -s53, fill=m5) +c41 = mcdc.cell(+s21 & -s22 & +s51 & -s52, fill=mvoid) +c42 = mcdc.cell(+s1 & -s20 & +s51 & -s53, fill=mvoid) +c43 = mcdc.cell(+s22 & -s40 & +s51 & -s53, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-2.py b/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-2.py new file mode 100644 index 0000000..a16d0c6 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-2.py @@ -0,0 +1,176 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.045694], + ['U238',0.001335], + ['C0',7.456e-05], + ['Fe54',1.054438e-06], + ['Fe56',1.65524216e-05], + ['Fe57',3.822676e-07], + ['Fe58',5.08728e-08], + ['W180',1.095984e-09], + ['W182',2.420298e-07], + ['W183',1.30696092e-07], + ['W184',2.79841248e-07], + ['W186',2.59656876e-07]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.03929], + ['H1',0.078579]]) +# Material Name: Titanium +m3 = mcdc.material(nuclides=[ + ['Ti46',0.00467214], + ['Ti47',0.0042134208], + ['Ti48',0.0417491104], + ['Ti49',0.0030637912000000002], + ['Ti50',0.0029335376], + ['Al27',0.0010151]]) +# Material Name: Aluminium +m4 = mcdc.material(nuclides=[ + ['Al27',0.059154], + ['Mn55',0.00038519], + ['Si28',0.000160359744616], + ['Si29',8.142610292e-06], + ['Si30',5.367645092e-06], + ['Fe54',5.963069000000001e-06], + ['Fe56',9.36074308e-05], + ['Fe57',2.1618038e-06], + ['Fe58',2.8769640000000003e-07]]) +# Material Name: Steel +m5 = mcdc.material(nuclides=[ + ['Fe54',0.00484006915], + ['Fe56',0.07597873478], + ['Fe57',0.0017546803300000002], + ['Fe58',0.00023351574000000003], + ['C0',0.00040815], + ['Si28',0.000413954472744], + ['Si29',2.1019427028e-05], + ['Si30',1.3856100228e-05], + ['Mn55',0.00042492], + ['Cr50',2.9261402500000003e-06], + ['Cr52',5.642770205e-05], + ['Cr53',6.398448449999999e-06], + ['Cr54',1.5927092500000001e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-21.24, bc='vacuum') +s2 = mcdc.surface('plane-z', z=-20.75, bc='interface') +s3 = mcdc.surface('plane-z', z=-18.78, bc='interface') +s4 = mcdc.surface('plane-z', z=-18.29, bc='interface') +s5 = mcdc.surface('plane-z', z=-16.3, bc='interface') +s6 = mcdc.surface('plane-z', z=-15.81, bc='interface') +s7 = mcdc.surface('plane-z', z=-13.84, bc='interface') +s8 = mcdc.surface('plane-z', z=-13.35, bc='interface') +s9 = mcdc.surface('plane-z', z=-11.36, bc='interface') +s10 = mcdc.surface('plane-z', z=-10.87, bc='interface') +s11 = mcdc.surface('plane-z', z=-8.9, bc='interface') +s12 = mcdc.surface('plane-z', z=-8.41, bc='interface') +s13 = mcdc.surface('plane-z', z=-6.42, bc='interface') +s14 = mcdc.surface('plane-z', z=-5.93, bc='interface') +s15 = mcdc.surface('plane-z', z=-3.96, bc='interface') +s16 = mcdc.surface('plane-z', z=-3.47, bc='interface') +s17 = mcdc.surface('plane-z', z=-1.48, bc='interface') +s18 = mcdc.surface('plane-z', z=-0.99, bc='interface') +s19 = mcdc.surface('plane-z', z=0.0, bc='interface') +s20 = mcdc.surface('plane-z', z=1.26, bc='interface') +s21 = mcdc.surface('plane-z', z=1.46, bc='interface') +s22 = mcdc.surface('plane-z', z=2.06, bc='interface') +s23 = mcdc.surface('plane-z', z=2.24, bc='interface') +s24 = mcdc.surface('plane-z', z=2.73, bc='interface') +s25 = mcdc.surface('plane-z', z=4.72, bc='interface') +s26 = mcdc.surface('plane-z', z=5.21, bc='interface') +s27 = mcdc.surface('plane-z', z=7.18, bc='interface') +s28 = mcdc.surface('plane-z', z=7.67, bc='interface') +s29 = mcdc.surface('plane-z', z=9.66, bc='interface') +s30 = mcdc.surface('plane-z', z=10.15, bc='interface') +s31 = mcdc.surface('plane-z', z=12.12, bc='interface') +s32 = mcdc.surface('plane-z', z=12.61, bc='interface') +s33 = mcdc.surface('plane-z', z=14.6, bc='interface') +s34 = mcdc.surface('plane-z', z=15.09, bc='interface') +s35 = mcdc.surface('plane-z', z=17.06, bc='interface') +s36 = mcdc.surface('plane-z', z=17.55, bc='interface') +s37 = mcdc.surface('plane-z', z=19.54, bc='interface') +s38 = mcdc.surface('plane-z', z=20.03, bc='interface') +s39 = mcdc.surface('plane-z', z=22.0, bc='interface') +s40 = mcdc.surface('plane-z', z=22.49, bc='vacuum') +s50 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.6, bc='interface') +s51 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.995, bc='interface') +s52 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.0, bc='interface') +s53 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s51, fill=m4) +c2 = mcdc.cell(+s2 & -s3 & -s51, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s51, fill=m4) +c4 = mcdc.cell(+s4 & -s5 & -s51, fill=m1) +c5 = mcdc.cell(+s5 & -s6 & -s51, fill=m4) +c6 = mcdc.cell(+s6 & -s7 & -s51, fill=m2) +c7 = mcdc.cell(+s7 & -s8 & -s51, fill=m4) +c8 = mcdc.cell(+s8 & -s9 & -s51, fill=m1) +c9 = mcdc.cell(+s9 & -s10 & -s51, fill=m4) +c10 = mcdc.cell(+s10 & -s11 & -s51, fill=m2) +c11 = mcdc.cell(+s11 & -s12 & -s51, fill=m4) +c12 = mcdc.cell(+s12 & -s13 & -s51, fill=m1) +c13 = mcdc.cell(+s13 & -s14 & -s51, fill=m4) +c14 = mcdc.cell(+s14 & -s15 & -s51, fill=m2) +c15 = mcdc.cell(+s15 & -s16 & -s51, fill=m4) +c16 = mcdc.cell(+s16 & -s17 & -s51, fill=m1) +c17 = mcdc.cell(+s17 & -s18 & -s51, fill=m4) +c18 = mcdc.cell(+s18 & -s19 & +s50 & -s51, fill=m2) +c19 = mcdc.cell(+s18 & -s19 & -s50, fill=mvoid) +c20 = mcdc.cell(+s19 & -s20 & -s51, fill=mvoid) +c21 = mcdc.cell(+s20 & -s23 & -s51, fill=m2) +c22 = mcdc.cell(+s23 & -s24 & -s51, fill=m4) +c23 = mcdc.cell(+s24 & -s25 & -s51, fill=m1) +c24 = mcdc.cell(+s25 & -s26 & -s51, fill=m4) +c25 = mcdc.cell(+s26 & -s27 & -s51, fill=m2) +c26 = mcdc.cell(+s27 & -s28 & -s51, fill=m4) +c27 = mcdc.cell(+s28 & -s29 & -s51, fill=m1) +c28 = mcdc.cell(+s29 & -s30 & -s51, fill=m4) +c29 = mcdc.cell(+s30 & -s31 & -s51, fill=m2) +c30 = mcdc.cell(+s31 & -s32 & -s51, fill=m4) +c31 = mcdc.cell(+s32 & -s33 & -s51, fill=m1) +c32 = mcdc.cell(+s33 & -s34 & -s51, fill=m4) +c33 = mcdc.cell(+s34 & -s35 & -s51, fill=m2) +c34 = mcdc.cell(+s35 & -s36 & -s51, fill=m4) +c35 = mcdc.cell(+s36 & -s37 & -s51, fill=m1) +c36 = mcdc.cell(+s37 & -s38 & -s51, fill=m4) +c37 = mcdc.cell(+s38 & -s39 & -s51, fill=m2) +c38 = mcdc.cell(+s39 & -s40 & -s51, fill=m4) +c39 = mcdc.cell(+s20 & -s21 & +s51 & -s52, fill=m5) +c40 = mcdc.cell(+s20 & -s22 & +s52 & -s53, fill=m5) +c41 = mcdc.cell(+s21 & -s22 & +s51 & -s52, fill=mvoid) +c42 = mcdc.cell(+s1 & -s20 & +s51 & -s53, fill=mvoid) +c43 = mcdc.cell(+s22 & -s40 & +s51 & -s53, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-3.py b/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-3.py new file mode 100644 index 0000000..0739f93 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/mcdc/heu-met-fast-034_case-3.py @@ -0,0 +1,176 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.045694], + ['U238',0.001335], + ['C0',7.456e-05], + ['Fe54',1.054438e-06], + ['Fe56',1.65524216e-05], + ['Fe57',3.822676e-07], + ['Fe58',5.08728e-08], + ['W180',1.095984e-09], + ['W182',2.420298e-07], + ['W183',1.30696092e-07], + ['W184',2.79841248e-07], + ['W186',2.59656876e-07]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.03929], + ['H1',0.078579]]) +# Material Name: Titanium +m3 = mcdc.material(nuclides=[ + ['Ti46',0.00467214], + ['Ti47',0.0042134208], + ['Ti48',0.0417491104], + ['Ti49',0.0030637912000000002], + ['Ti50',0.0029335376], + ['Al27',0.0010151]]) +# Material Name: Aluminium +m4 = mcdc.material(nuclides=[ + ['Al27',0.059154], + ['Mn55',0.00038519], + ['Si28',0.000160359744616], + ['Si29',8.142610292e-06], + ['Si30',5.367645092e-06], + ['Fe54',5.963069000000001e-06], + ['Fe56',9.36074308e-05], + ['Fe57',2.1618038e-06], + ['Fe58',2.8769640000000003e-07]]) +# Material Name: Steel +m5 = mcdc.material(nuclides=[ + ['Fe54',0.00484006915], + ['Fe56',0.07597873478], + ['Fe57',0.0017546803300000002], + ['Fe58',0.00023351574000000003], + ['C0',0.00040815], + ['Si28',0.000413954472744], + ['Si29',2.1019427028e-05], + ['Si30',1.3856100228e-05], + ['Mn55',0.00042492], + ['Cr50',2.9261402500000003e-06], + ['Cr52',5.642770205e-05], + ['Cr53',6.398448449999999e-06], + ['Cr54',1.5927092500000001e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-21.24, bc='vacuum') +s2 = mcdc.surface('plane-z', z=-20.75, bc='interface') +s3 = mcdc.surface('plane-z', z=-18.78, bc='interface') +s4 = mcdc.surface('plane-z', z=-18.29, bc='interface') +s5 = mcdc.surface('plane-z', z=-16.3, bc='interface') +s6 = mcdc.surface('plane-z', z=-15.81, bc='interface') +s7 = mcdc.surface('plane-z', z=-13.84, bc='interface') +s8 = mcdc.surface('plane-z', z=-13.35, bc='interface') +s9 = mcdc.surface('plane-z', z=-11.36, bc='interface') +s10 = mcdc.surface('plane-z', z=-10.87, bc='interface') +s11 = mcdc.surface('plane-z', z=-8.9, bc='interface') +s12 = mcdc.surface('plane-z', z=-8.41, bc='interface') +s13 = mcdc.surface('plane-z', z=-6.42, bc='interface') +s14 = mcdc.surface('plane-z', z=-5.93, bc='interface') +s15 = mcdc.surface('plane-z', z=-3.96, bc='interface') +s16 = mcdc.surface('plane-z', z=-3.47, bc='interface') +s17 = mcdc.surface('plane-z', z=-1.48, bc='interface') +s18 = mcdc.surface('plane-z', z=-0.99, bc='interface') +s19 = mcdc.surface('plane-z', z=0.0, bc='interface') +s20 = mcdc.surface('plane-z', z=1.11, bc='interface') +s21 = mcdc.surface('plane-z', z=1.31, bc='interface') +s22 = mcdc.surface('plane-z', z=1.91, bc='interface') +s23 = mcdc.surface('plane-z', z=2.09, bc='interface') +s24 = mcdc.surface('plane-z', z=2.58, bc='interface') +s25 = mcdc.surface('plane-z', z=4.57, bc='interface') +s26 = mcdc.surface('plane-z', z=5.06, bc='interface') +s27 = mcdc.surface('plane-z', z=7.03, bc='interface') +s28 = mcdc.surface('plane-z', z=7.52, bc='interface') +s29 = mcdc.surface('plane-z', z=9.51, bc='interface') +s30 = mcdc.surface('plane-z', z=10.0, bc='interface') +s31 = mcdc.surface('plane-z', z=11.97, bc='interface') +s32 = mcdc.surface('plane-z', z=12.46, bc='interface') +s33 = mcdc.surface('plane-z', z=14.45, bc='interface') +s34 = mcdc.surface('plane-z', z=14.94, bc='interface') +s35 = mcdc.surface('plane-z', z=16.91, bc='interface') +s36 = mcdc.surface('plane-z', z=17.4, bc='interface') +s37 = mcdc.surface('plane-z', z=19.39, bc='interface') +s38 = mcdc.surface('plane-z', z=19.88, bc='interface') +s39 = mcdc.surface('plane-z', z=21.85, bc='interface') +s40 = mcdc.surface('plane-z', z=22.34, bc='vacuum') +s50 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.6, bc='interface') +s51 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.995, bc='interface') +s52 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.0, bc='interface') +s53 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s51, fill=m5) +c2 = mcdc.cell(+s2 & -s3 & -s51, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & -s51, fill=m5) +c4 = mcdc.cell(+s4 & -s5 & -s51, fill=m1) +c5 = mcdc.cell(+s5 & -s6 & -s51, fill=m5) +c6 = mcdc.cell(+s6 & -s7 & -s51, fill=m2) +c7 = mcdc.cell(+s7 & -s8 & -s51, fill=m5) +c8 = mcdc.cell(+s8 & -s9 & -s51, fill=m1) +c9 = mcdc.cell(+s9 & -s10 & -s51, fill=m5) +c10 = mcdc.cell(+s10 & -s11 & -s51, fill=m2) +c11 = mcdc.cell(+s11 & -s12 & -s51, fill=m5) +c12 = mcdc.cell(+s12 & -s13 & -s51, fill=m1) +c13 = mcdc.cell(+s13 & -s14 & -s51, fill=m5) +c14 = mcdc.cell(+s14 & -s15 & -s51, fill=m2) +c15 = mcdc.cell(+s15 & -s16 & -s51, fill=m5) +c16 = mcdc.cell(+s16 & -s17 & -s51, fill=m1) +c17 = mcdc.cell(+s17 & -s18 & -s51, fill=m5) +c18 = mcdc.cell(+s18 & -s19 & +s50 & -s51, fill=m2) +c19 = mcdc.cell(+s18 & -s19 & -s50, fill=mvoid) +c20 = mcdc.cell(+s19 & -s20 & -s51, fill=mvoid) +c21 = mcdc.cell(+s20 & -s23 & -s51, fill=m2) +c22 = mcdc.cell(+s23 & -s24 & -s51, fill=m5) +c23 = mcdc.cell(+s24 & -s25 & -s51, fill=m1) +c24 = mcdc.cell(+s25 & -s26 & -s51, fill=m5) +c25 = mcdc.cell(+s26 & -s27 & -s51, fill=m2) +c26 = mcdc.cell(+s27 & -s28 & -s51, fill=m5) +c27 = mcdc.cell(+s28 & -s29 & -s51, fill=m1) +c28 = mcdc.cell(+s29 & -s30 & -s51, fill=m5) +c29 = mcdc.cell(+s30 & -s31 & -s51, fill=m2) +c30 = mcdc.cell(+s31 & -s32 & -s51, fill=m5) +c31 = mcdc.cell(+s32 & -s33 & -s51, fill=m1) +c32 = mcdc.cell(+s33 & -s34 & -s51, fill=m5) +c33 = mcdc.cell(+s34 & -s35 & -s51, fill=m2) +c34 = mcdc.cell(+s35 & -s36 & -s51, fill=m5) +c35 = mcdc.cell(+s36 & -s37 & -s51, fill=m1) +c36 = mcdc.cell(+s37 & -s38 & -s51, fill=m5) +c37 = mcdc.cell(+s38 & -s39 & -s51, fill=m2) +c38 = mcdc.cell(+s39 & -s40 & -s51, fill=m5) +c39 = mcdc.cell(+s20 & -s21 & +s51 & -s52, fill=m5) +c40 = mcdc.cell(+s20 & -s22 & +s52 & -s53, fill=m5) +c41 = mcdc.cell(+s21 & -s22 & +s51 & -s52, fill=mvoid) +c42 = mcdc.cell(+s1 & -s20 & +s51 & -s53, fill=mvoid) +c43 = mcdc.cell(+s22 & -s40 & +s51 & -s53, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-034/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..ad9c583 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-1/generate_materials.py @@ -0,0 +1,50 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.5694e-02) +mat.add_nuclide('U238', 1.3350e-03) +mat.add_nuclide('U234', 5.6419e-04) +mat.add_element('C', 7.4560e-05) +mat.add_element('Fe', 1.8040e-05) +mat.add_element('W', 9.1332e-07) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9290e-02) +mat.add_nuclide('H1', 7.8579e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Titanium" +mat.set_density('sum') +mat.add_element('Ti', 5.6632e-02) +mat.add_element('Al', 1.0151e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Aluminium" +mat.set_density('sum') +mat.add_element('Al', 5.9154e-02) +mat.add_element('Mn', 3.8519e-04) +mat.add_element('Si', 1.7387e-04) +mat.add_element('Fe', 1.0202e-04) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Steel" +mat.set_density('sum') +mat.add_element('Fe', 8.2807e-02) +mat.add_element('C', 4.0815e-04) +mat.add_element('Si', 4.4883e-04) +mat.add_element('Mn', 4.2492e-04) +mat.add_element('Cr', 6.7345e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-1/geometry.xml new file mode 100644 index 0000000..dd95504 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-1/geometry.xml @@ -0,0 +1,113 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-1/materials.xml new file mode 100644 index 0000000..1c4ae53 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-1/materials.xml @@ -0,0 +1,62 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-034/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..ad9c583 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-2/generate_materials.py @@ -0,0 +1,50 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.5694e-02) +mat.add_nuclide('U238', 1.3350e-03) +mat.add_nuclide('U234', 5.6419e-04) +mat.add_element('C', 7.4560e-05) +mat.add_element('Fe', 1.8040e-05) +mat.add_element('W', 9.1332e-07) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9290e-02) +mat.add_nuclide('H1', 7.8579e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Titanium" +mat.set_density('sum') +mat.add_element('Ti', 5.6632e-02) +mat.add_element('Al', 1.0151e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Aluminium" +mat.set_density('sum') +mat.add_element('Al', 5.9154e-02) +mat.add_element('Mn', 3.8519e-04) +mat.add_element('Si', 1.7387e-04) +mat.add_element('Fe', 1.0202e-04) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Steel" +mat.set_density('sum') +mat.add_element('Fe', 8.2807e-02) +mat.add_element('C', 4.0815e-04) +mat.add_element('Si', 4.4883e-04) +mat.add_element('Mn', 4.2492e-04) +mat.add_element('Cr', 6.7345e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-2/geometry.xml new file mode 100644 index 0000000..719df8e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-2/geometry.xml @@ -0,0 +1,113 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-2/materials.xml new file mode 100644 index 0000000..1c4ae53 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-2/materials.xml @@ -0,0 +1,62 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-met-fast-034/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..ad9c583 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-3/generate_materials.py @@ -0,0 +1,50 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.5694e-02) +mat.add_nuclide('U238', 1.3350e-03) +mat.add_nuclide('U234', 5.6419e-04) +mat.add_element('C', 7.4560e-05) +mat.add_element('Fe', 1.8040e-05) +mat.add_element('W', 9.1332e-07) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9290e-02) +mat.add_nuclide('H1', 7.8579e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Titanium" +mat.set_density('sum') +mat.add_element('Ti', 5.6632e-02) +mat.add_element('Al', 1.0151e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Aluminium" +mat.set_density('sum') +mat.add_element('Al', 5.9154e-02) +mat.add_element('Mn', 3.8519e-04) +mat.add_element('Si', 1.7387e-04) +mat.add_element('Fe', 1.0202e-04) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Steel" +mat.set_density('sum') +mat.add_element('Fe', 8.2807e-02) +mat.add_element('C', 4.0815e-04) +mat.add_element('Si', 4.4883e-04) +mat.add_element('Mn', 4.2492e-04) +mat.add_element('Cr', 6.7345e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-3/geometry.xml new file mode 100644 index 0000000..1d977bd --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-3/geometry.xml @@ -0,0 +1,113 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-3/materials.xml new file mode 100644 index 0000000..1c4ae53 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-3/materials.xml @@ -0,0 +1,62 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-034/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-034/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-met-fast-034/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-1.py b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-1.py new file mode 100644 index 0000000..e26f7f2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-1.py @@ -0,0 +1,48 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044508], + ['U238',0.0023775]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.73197, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.43097, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-2.py b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-2.py new file mode 100644 index 0000000..2d253f0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-2.py @@ -0,0 +1,48 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044605], + ['U238',0.0025315]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.64241, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.42801, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-3.py b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-3.py new file mode 100644 index 0000000..e60a80d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-3.py @@ -0,0 +1,48 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044989], + ['U238',0.0024032]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.083731]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.38298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.46298, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-4.py b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-4.py new file mode 100644 index 0000000..43e42d8 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-4.py @@ -0,0 +1,48 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044989], + ['U238',0.0024032]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.083731]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.91306, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.07306, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-5.py b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-5.py new file mode 100644 index 0000000..429d8fe --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-5.py @@ -0,0 +1,48 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044388], + ['U238',0.002371]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.083731]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.66647, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=21.90647, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-6.py b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-6.py new file mode 100644 index 0000000..22f04eb --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/mcdc/heu-met-fast-041_case-6.py @@ -0,0 +1,48 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.04501], + ['U238',0.0024096]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.083731]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.41839, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=26.73839, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-041/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..b9b0154 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-1/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8554e-04) +mat.add_nuclide('U235', 4.4508e-02) +mat.add_nuclide('U238', 2.3775e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-1/geometry.xml new file mode 100644 index 0000000..d2b9536 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-1/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-1/materials.xml new file mode 100644 index 0000000..0b45d75 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-1/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-041/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..4793e9e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-2/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8817e-04) +mat.add_nuclide('U235', 4.4605e-02) +mat.add_nuclide('U238', 2.5315e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-2/geometry.xml new file mode 100644 index 0000000..9f1f64c --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-2/materials.xml new file mode 100644 index 0000000..1535263 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-2/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-met-fast-041/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..e927033 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-3/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9079e-04) +mat.add_nuclide('U235', 4.4989e-02) +mat.add_nuclide('U238', 2.4032e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.3731e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-3/geometry.xml new file mode 100644 index 0000000..287330a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-3/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-3/materials.xml new file mode 100644 index 0000000..b01ec36 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-3/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-3/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-met-fast-041/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..e927033 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-4/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9079e-04) +mat.add_nuclide('U235', 4.4989e-02) +mat.add_nuclide('U238', 2.4032e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.3731e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-4/geometry.xml new file mode 100644 index 0000000..d507eed --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-4/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-4/materials.xml new file mode 100644 index 0000000..b01ec36 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-4/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-4/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-met-fast-041/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..1b80aed --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-5/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8423e-04) +mat.add_nuclide('U235', 4.4388e-02) +mat.add_nuclide('U238', 2.3710e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.3731e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-5/geometry.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-5/geometry.xml new file mode 100644 index 0000000..47934e8 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-5/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-5/materials.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-5/materials.xml new file mode 100644 index 0000000..c092627 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-5/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-5/settings.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-5/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-met-fast-041/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..c0b15b0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-6/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9210e-04) +mat.add_nuclide('U235', 4.5010e-02) +mat.add_nuclide('U238', 2.4096e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.3731e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-6/geometry.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-6/geometry.xml new file mode 100644 index 0000000..c9bcdaa --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-6/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-6/materials.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-6/materials.xml new file mode 100644 index 0000000..4a55772 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-6/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-041/openmc/case-6/settings.xml b/icsbep/openmc/heu-met-fast-041/openmc/case-6/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-041/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-1.py b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-1.py new file mode 100644 index 0000000..1f0d1c5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-1.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (internal) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: HEU +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.044197], + ['U238',0.0027295]]) +# Material Name: Beryllium (outer) +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.1805, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=25.4497, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-2.py b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-2.py new file mode 100644 index 0000000..06d6300 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-2.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (internal) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: HEU +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.044267], + ['U238',0.002735]]) +# Material Name: Beryllium (outer) +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.94, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.211, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-3.py b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-3.py new file mode 100644 index 0000000..bec7558 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-3.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (internal) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: HEU +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.044307], + ['U238',0.0027374]]) +# Material Name: Beryllium (outer) +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5445, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.9801, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-4.py b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-4.py new file mode 100644 index 0000000..daf55aa --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-4.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (internal) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: HEU +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.044392], + ['U238',0.0027427]]) +# Material Name: Beryllium (outer) +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.1105, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.3744, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-5.py b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-5.py new file mode 100644 index 0000000..9958927 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/mcdc/heu-met-fast-058_case-5.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (internal) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: HEU +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.0445], + ['U238',0.0027494]]) +# Material Name: Beryllium (outer) +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.479, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.7015, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-058/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..8192835 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-1/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (internal)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7621e-04) +mat.add_nuclide('U235', 4.4197e-02) +mat.add_nuclide('U238', 2.7295e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Beryllium (outer)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-1/geometry.xml new file mode 100644 index 0000000..13de9b8 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-1/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-1/materials.xml new file mode 100644 index 0000000..3c1276f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-058/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..911b2d2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-2/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (internal)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7716e-04) +mat.add_nuclide('U235', 4.4267e-02) +mat.add_nuclide('U238', 2.7350e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Beryllium (outer)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-2/geometry.xml new file mode 100644 index 0000000..f7c60a5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-2/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-2/materials.xml new file mode 100644 index 0000000..3948b98 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-met-fast-058/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..465f7a1 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-3/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (internal)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7759e-04) +mat.add_nuclide('U235', 4.4307e-02) +mat.add_nuclide('U238', 2.7374e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Beryllium (outer)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-3/geometry.xml new file mode 100644 index 0000000..26818cf --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-3/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-3/materials.xml new file mode 100644 index 0000000..4e8aaf7 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-3/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-met-fast-058/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..e91deec --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-4/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (internal)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7851e-04) +mat.add_nuclide('U235', 4.4392e-02) +mat.add_nuclide('U238', 2.7427e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Beryllium (outer)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-4/geometry.xml new file mode 100644 index 0000000..bc82f2f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-4/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-4/materials.xml new file mode 100644 index 0000000..146ebb8 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-4/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-met-fast-058/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..a0a7688 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-5/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (internal)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7967e-04) +mat.add_nuclide('U235', 4.4500e-02) +mat.add_nuclide('U238', 2.7494e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Beryllium (outer)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-5/geometry.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-5/geometry.xml new file mode 100644 index 0000000..240f5c5 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-5/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-5/materials.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-5/materials.xml new file mode 100644 index 0000000..0fdbb1b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-058/openmc/case-5/settings.xml b/icsbep/openmc/heu-met-fast-058/openmc/case-5/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-058/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-1.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-1.py new file mode 100644 index 0000000..6324d09 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-1.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044268], + ['U238',0.002735]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.146, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5445, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.2845, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-2.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-2.py new file mode 100644 index 0000000..bbbd5b1 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-2.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044371], + ['U238',0.0027414]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.146, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.1105, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.3905, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-3.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-3.py new file mode 100644 index 0000000..e7f6480 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-3.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044491], + ['U238',0.0027488]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.146, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.479, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.339, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-4.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-4.py new file mode 100644 index 0000000..eb390b1 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-4.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044368], + ['U238',0.0027412]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0895, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5445, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.7445, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-5.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-5.py new file mode 100644 index 0000000..ac87de0 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-5.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044456], + ['U238',0.0027467]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0895, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.1105, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.9605, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-6.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-6.py new file mode 100644 index 0000000..4289a31 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-6.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044575], + ['U238',0.002754]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0895, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.479, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.119, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-7.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-7.py new file mode 100644 index 0000000..345d372 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-7.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044628], + ['U238',0.0027573]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6975, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.479, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.149, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-8.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-8.py new file mode 100644 index 0000000..c67e734 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-8.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.044505], + ['U238',0.0027497]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6975, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.1105, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7505, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-9.py b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-9.py new file mode 100644 index 0000000..1a3c70e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/mcdc/heu-met-fast-066_case-9.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Beryllium (source) +# S(a,b): c_Be (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['Be9',0.11862]]) +# Material Name: Nickel +m2 = mcdc.material(nuclides=[ + ['Ni58',0.06214740200999999], + ['Ni60',0.023939067989999993], + ['Ni61',0.0010406147099999998], + ['Ni62',0.0033179350500000004], + ['Ni64',0.0008449802400000001]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8453626515e-05], + ['N15',1.41373485e-07], + ['O16',1.0382063706e-05], + ['O17',3.936294e-09], + ['Ar36',1.5398976e-09], + ['Ar38',2.9034640000000003e-10], + ['Ar40',4.59769756e-07], + ['C0',1.6307e-08]]) +# Material Name: Beryllium (moderator/reflector) +# S(a,b): c_Be (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +# Material Name: HEU +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.043932], + ['U238',0.0027143]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.4983, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5207, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.5555, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5545, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.139, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.629, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..a9629ff --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-1/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7717e-04) +mat.add_nuclide('U235', 4.4268e-02) +mat.add_nuclide('U238', 2.7350e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-1/geometry.xml new file mode 100644 index 0000000..77a0cfd --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-1/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-1/materials.xml new file mode 100644 index 0000000..f618f01 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..941b7c1 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-2/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7828e-04) +mat.add_nuclide('U235', 4.4371e-02) +mat.add_nuclide('U238', 2.7414e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-2/geometry.xml new file mode 100644 index 0000000..f83490e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-2/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-2/materials.xml new file mode 100644 index 0000000..0e1bec1 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..a1dfaaf --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-3/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7957e-04) +mat.add_nuclide('U235', 4.4491e-02) +mat.add_nuclide('U238', 2.7488e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-3/geometry.xml new file mode 100644 index 0000000..4057be4 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-3/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-3/materials.xml new file mode 100644 index 0000000..4e658fb --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-3/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..fc70932 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-4/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7824e-04) +mat.add_nuclide('U235', 4.4368e-02) +mat.add_nuclide('U238', 2.7412e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-4/geometry.xml new file mode 100644 index 0000000..6a0517f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-4/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-4/materials.xml new file mode 100644 index 0000000..e97ee38 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-4/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..a4438c2 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-5/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7920e-04) +mat.add_nuclide('U235', 4.4456e-02) +mat.add_nuclide('U238', 2.7467e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-5/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-5/geometry.xml new file mode 100644 index 0000000..32a800b --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-5/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-5/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-5/materials.xml new file mode 100644 index 0000000..b3a8aba --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-5/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-5/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..1e7661e --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-6/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8048e-04) +mat.add_nuclide('U235', 4.4575e-02) +mat.add_nuclide('U238', 2.7540e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-6/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-6/geometry.xml new file mode 100644 index 0000000..e23cd0f --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-6/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-6/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-6/materials.xml new file mode 100644 index 0000000..e876496 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-6/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-6/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-7/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..db729c4 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-7/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8105e-04) +mat.add_nuclide('U235', 4.4628e-02) +mat.add_nuclide('U238', 2.7573e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-7/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-7/geometry.xml new file mode 100644 index 0000000..9ca655a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-7/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-7/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-7/materials.xml new file mode 100644 index 0000000..0d31d74 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-7/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-7/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-7/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-8/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..3497614 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-8/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7972e-04) +mat.add_nuclide('U235', 4.4505e-02) +mat.add_nuclide('U238', 2.7497e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-8/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-8/geometry.xml new file mode 100644 index 0000000..4150b95 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-8/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-8/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-8/materials.xml new file mode 100644 index 0000000..82b8613 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-8/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-8/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-8/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-9/generate_materials.py b/icsbep/openmc/heu-met-fast-066/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..b58ca61 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-9/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Beryllium (source)" +mat.set_density('sum') +mat.add_element('Be', 1.1862e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel" +mat.set_density('sum') +mat.add_element('Ni', 9.1290e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.8595e-05) +mat.add_element('O', 1.0386e-05) +mat.add_element('Ar', 4.6160e-07) +mat.add_element('C', 1.6307e-08) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Beryllium (moderator/reflector)" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.7355e-04) +mat.add_nuclide('U235', 4.3932e-02) +mat.add_nuclide('U238', 2.7143e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-9/geometry.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-9/geometry.xml new file mode 100644 index 0000000..4c89d3d --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-9/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-9/materials.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-9/materials.xml new file mode 100644 index 0000000..b1f0e7a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-9/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-066/openmc/case-9/settings.xml b/icsbep/openmc/heu-met-fast-066/openmc/case-9/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-066/openmc/case-9/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-069/mcdc/heu-met-fast-069_case-1.py b/icsbep/openmc/heu-met-fast-069/mcdc/heu-met-fast-069_case-1.py new file mode 100644 index 0000000..e730570 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/mcdc/heu-met-fast-069_case-1.py @@ -0,0 +1,631 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU part 2732 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044692], + ['U238',0.0026854], + ['Ag107',4.336747062000001e-07], + ['Ag109',4.0290529380000004e-07], + ['Ba130',4.5177e-13], + ['Ba132',4.107e-13], + ['Ba134',9.938939999999999e-12], + ['Ba135',2.706513e-11], + ['Ba136',3.223995e-11], + ['Ba137',4.612161e-11], + ['Ba138',2.944719e-10], + ['Bi209',8.8522e-06], + ['C0',4.6957e-06], + ['Ca40',2.728404445e-08], + ['Ca42',1.8209815e-10], + ['Ca43',3.799575000000001e-11], + ['Ca44',5.871047e-10], + ['Ca46',1.1258000000000001e-12], + ['Ca48',5.263115e-11], + ['Cd106',6.246663e-10], + ['Cd108',4.4554512e-10], + ['Cd110',6.256697800000001e-09], + ['Cd111',6.4197633e-09], + ['Cd112',1.2096449660000001e-08], + ['Cd113',6.1347749800000006e-09], + ['Cd114',1.4427031960000002e-08], + ['Cd116',3.76907088e-09], + ['Co59',9.5702e-07], + ['Cr50',6.598317e-08], + ['Cr52',1.272419754e-06], + ['Cr53',1.4428218599999998e-07], + ['Cr54',3.591489e-08], + ['Cu63',3.0687386999999997e-06], + ['Cu65',1.3690613e-06], + ['K39',2.6905894431000002e-08], + ['K40',3.3755670000000002e-12], + ['K41',1.941730002e-09], + ['Li6',1.23328839e-07], + ['Li7',1.5017711609999999e-06], + ['Mg24',1.099234773e-06], + ['Mg25',1.3950846e-07], + ['Mg26',1.53556767e-07], + ['Mn55',1.1498e-05], + ['Mo100',5.72820528e-09], + ['Mo92',8.61170763e-09], + ['Mo94',5.40076169e-09], + ['Mo95',9.331260510000001e-09], + ['Mo96',9.80155651e-09], + ['Mo97',5.6329703400000005e-09], + ['Mo98',1.428053804e-08], + ['Na23',1.3248e-05], + ['Ni58',1.3084380179999998e-05], + ['Ni60',5.0400798199999995e-06], + ['Ni61',2.1908877999999998e-07], + ['Ni62',6.985509000000001e-07], + ['Ni64',1.7790032e-07], + ['Sb121',2.01419247e-06], + ['Sb123',1.50650753e-06], + ['Ti46',1.9436175000000002e-08], + ['Ti47',1.7527896e-08], + ['Ti48',1.73676948e-07], + ['Ti49',1.2745419e-08], + ['Ti50',1.2203562e-08], + ['O16',1.4095655720999998e-05], + ['O17',5.344278999999999e-09], + ['N14',2.407150192e-05], + ['N15',8.849808e-08]]) +# Material Name: HEU part 2733 +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044702], + ['U238',0.0026677], + ['Ag107',4.3387169440000004e-07], + ['Ag109',4.030883056e-07], + ['Ba130',4.51979e-13], + ['Ba132',4.1089e-13], + ['Ba134',9.943538e-12], + ['Ba135',2.7077651e-11], + ['Ba136',3.2254865e-11], + ['Ba137',4.6142947000000003e-11], + ['Ba138',2.9460813e-10], + ['Bi209',8.8562e-06], + ['C0',4.6978e-06], + ['Ca40',2.729664678e-08], + ['Ca42',1.8218225999999997e-10], + ['Ca43',3.8013300000000005e-11], + ['Ca44',5.8737588e-10], + ['Ca46',1.12632e-12], + ['Ca48',5.2655460000000005e-11], + ['Cd106',6.249402e-10], + ['Cd108',4.4574048e-10], + ['Cd110',6.2594412e-09], + ['Cd111',6.4225782e-09], + ['Cd112',1.210175364e-08], + ['Cd113',6.1374649200000004e-09], + ['Cd114',1.4433357840000002e-08], + ['Cd116',3.77072352e-09], + ['Co59',9.5745e-07], + ['Cr50',6.6013585e-08], + ['Cr52',1.2730062770000001e-06], + ['Cr53',1.44348693e-07], + ['Cr54',3.5931445e-08], + ['Cu63',3.0701216999999996e-06], + ['Cu65',1.3696783e-06], + ['K39',2.6918017983999997e-08], + ['K40',3.377088e-12], + ['K41',1.942604928e-09], + ['Li6',1.23389551e-07], + ['Li7',1.5025104490000001e-06], + ['Mg24',1.0997084790000002e-06], + ['Mg25',1.3956858e-07], + ['Mg26',1.53622941e-07], + ['Mn55',1.1503e-05], + ['Mo100',5.73083616e-09], + ['Mo92',8.61566286e-09], + ['Mo94',5.4032421799999994e-09], + ['Mo95',9.33554622e-09], + ['Mo96',9.806058219999999e-09], + ['Mo97',5.63555748e-09], + ['Mo98',1.4287096879999999e-08], + ['Na23',1.3254e-05], + ['Ni58',1.3089826331999999e-05], + ['Ni60',5.042177668e-06], + ['Ni61',2.1917997199999996e-07], + ['Ni62',6.9884166e-07], + ['Ni64',1.7797436800000001e-07], + ['Sb121',2.0151078300000002e-06], + ['Sb123',1.5071921700000001e-06], + ['Ti46',1.944525e-08], + ['Ti47',1.7536079999999998e-08], + ['Ti48',1.7375804e-07], + ['Ti49',1.275137e-08], + ['Ti50',1.2209259999999999e-08], + ['O16',1.4101653447e-05], + ['O17',5.3465530000000004e-09], + ['N14',2.4082461627e-05], + ['N15',8.8538373e-08]]) +# Material Name: HEU part 2734 +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.044751], + ['U238',0.0026697], + ['Ag107',4.3420346400000003e-07], + ['Ag109',4.0339653599999995e-07], + ['Ba130',4.5232e-13], + ['Ba132',4.112e-13], + ['Ba134',9.95104e-12], + ['Ba135',2.7098080000000002e-11], + ['Ba136',3.22792e-11], + ['Ba137',4.617775999999999e-11], + ['Ba138',2.948304e-10], + ['Bi209',8.863e-06], + ['C0',4.7015e-06], + ['Ca40',2.7317973800000002e-08], + ['Ca42',1.8232460000000002e-10], + ['Ca43',3.8043000000000005e-11], + ['Ca44',5.878348e-10], + ['Ca46',1.1272e-12], + ['Ca48',5.26966e-11], + ['Cd106',6.2542575e-10], + ['Cd108',4.4608679999999997e-10], + ['Cd110',6.2643045e-09], + ['Cd111',6.42756825e-09], + ['Cd112',1.211115615e-08], + ['Cd113',6.1422334500000005e-09], + ['Cd114',1.4444571899999999e-08], + ['Cd116',3.7736532e-09], + ['Co59',9.5819e-07], + ['Cr50',6.606138000000001e-08], + ['Cr52',1.2739279560000002e-06], + ['Cr53',1.44453204e-07], + ['Cr54',3.5957460000000003e-08], + ['Cu63',3.0724728e-06], + ['Cu65',1.3707272e-06], + ['K39',2.6938534766000003e-08], + ['K40',3.3796619999999997e-12], + ['K41',1.9440855720000003e-09], + ['Li6',1.2348061900000001e-07], + ['Li7',1.5036193809999998e-06], + ['Mg24',1.10057694e-06], + ['Mg25',1.3967879999999998e-07], + ['Mg26',1.5374426e-07], + ['Mn55',1.1512e-05], + ['Mo100',5.73522096e-09], + ['Mo92',8.62225491e-09], + ['Mo94',5.4073763299999996e-09], + ['Mo95',9.34268907e-09], + ['Mo96',9.813561069999999e-09], + ['Mo97',5.63986938e-09], + ['Mo98',1.429802828e-08], + ['Na23',1.3264e-05], + ['Ni58',1.3100037866999997e-05], + ['Ni60',5.0461111329999995e-06], + ['Ni61',2.1935095699999997e-07], + ['Ni62',6.99386835e-07], + ['Ni64',1.78113208e-07], + ['Sb121',2.0166525e-06], + ['Sb123',1.5083475e-06], + ['Ti46',1.94601e-08], + ['Ti47',1.7549472e-08], + ['Ti48',1.7389073599999997e-07], + ['Ti49',1.2761108e-08], + ['Ti50',1.2218584e-08], + ['O16',1.4112649277999998e-05], + ['O17',5.350721999999999e-09], + ['N14',2.4101392030000004e-05], + ['N15',8.860797e-08]]) +# Material Name: HEU part 2768 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.044855], + ['U238',0.0027009], + ['Ag107',4.354061288e-07], + ['Ag109',4.045138712e-07], + ['Ba130',4.5357400000000004e-13], + ['Ba132',4.1234e-13], + ['Ba134',9.978628e-12], + ['Ba135',2.7173206e-11], + ['Ba136',3.236869e-11], + ['Ba137',4.6305782e-11], + ['Ba138',2.9564778e-10], + ['Bi209',8.8875e-06], + ['C0',4.7145e-06], + ['Ca40',2.7393587780000005e-08], + ['Ca42',1.8282926000000002e-10], + ['Ca43',3.81483e-11], + ['Ca44',5.8946188e-10], + ['Ca46',1.1303200000000002e-12], + ['Ca48',5.284246e-11], + ['Cd106',6.271563e-10], + ['Cd108',4.4732112000000004e-10], + ['Cd110',6.2816378e-09], + ['Cd111',6.4453533e-09], + ['Cd112',1.2144667660000001e-08], + ['Cd113',6.15922898e-09], + ['Cd114',1.448453996e-08], + ['Cd116',3.78409488e-09], + ['Co59',9.6084e-07], + ['Cr50',6.624387e-08], + ['Cr52',1.277447094e-06], + ['Cr53',1.44852246e-07], + ['Cr54',3.605679e-08], + ['Cu63',3.08097825e-06], + ['Cu65',1.37452175e-06], + ['K39',2.7013141246000004e-08], + ['K40',3.3890219999999996e-12], + ['K41',1.949469732e-09], + ['Li6',1.23822124e-07], + ['Li7',1.5077778760000002e-06], + ['Mg24',1.103656029e-06], + ['Mg25',1.4006958e-07], + ['Mg26',1.54174391e-07], + ['Mn55',1.1544e-05], + ['Mo100',5.751103679999999e-09], + ['Mo92',8.64613278e-09], + ['Mo94',5.422351139999999e-09], + ['Mo95',9.36856206e-09], + ['Mo96',9.840738059999998e-09], + ['Mo97',5.65548804e-09], + ['Mo98',1.433762424e-08], + ['Na23',1.3301e-05], + ['Ni58',1.3136118624000001e-05], + ['Ni60',5.060009376e-06], + ['Ni61',2.19955104e-07], + ['Ni62',7.0131312e-07], + ['Ni64',1.78603776e-07], + ['Sb121',2.02220187e-06], + ['Sb123',1.51249813e-06], + ['Ti46',1.9513725e-08], + ['Ti47',1.7597832e-08], + ['Ti48',1.7436991599999998e-07], + ['Ti49',1.2796273e-08], + ['Ti50',1.2252254e-08], + ['O16',1.4151634497e-05], + ['O17',5.365503e-09], + ['N14',2.4167150272e-05], + ['N15',8.8849728e-08]]) +# Material Name: 0.5in Be disc +# S(a,b): c_Be (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['Be9',0.11959], + ['Al27',2.436e-05], + ['B10',2.0083605999999997e-07], + ['B11',8.124639399999999e-07], + ['Bi209',2.6209e-06], + ['Br79',3.474373242e-09], + ['Br81',3.3803267580000002e-09], + ['C0',0.00010944], + ['Cd106',2.426505e-10], + ['Cd108',1.7307120000000002e-10], + ['Cd110',2.4304030000000003e-09], + ['Cd111',2.4937455000000002e-09], + ['Cd112',4.6988441e-09], + ['Cd113',2.3830423000000004e-09], + ['Cd114',5.6041546000000006e-09], + ['Cd116',1.4640888000000003e-09], + ['Dy156',3.775072e-12], + ['Dy158',6.40414e-12], + ['Dy160',1.57002548e-10], + ['Dy161',1.273345268e-09], + ['Dy162',1.7173206999999998e-09], + ['Dy163',1.6782891519999998e-09], + ['Dy164',1.90506312e-09], + ['Fe54',1.4904750000000001e-06], + ['Fe56',2.3397270000000002e-05], + ['Fe57',5.40345e-07], + ['Fe58',7.191e-08], + ['Gd152',1.39324e-11], + ['Gd154',1.5186316e-10], + ['Gd155',1.0309976e-09], + ['Gd156',1.42598114e-09], + ['Gd157',1.0902103e-09], + ['Gd158',1.7304040800000001e-09], + ['Gd160',1.52281132e-09], + ['Mg24',7.116722091000001e-06], + ['Mg25',9.0321282e-07], + ['Mg26',9.94165089e-07], + ['Ni58',1.2706553384999999e-08], + ['Ni60',4.894541614999999e-09], + ['Ni61',2.1276233499999998e-10], + ['Ni62',6.78379425e-10], + ['Ni64',1.7276324e-10], + ['O16',0.0008449696350899999], + ['O17',3.2036490999999996e-07], + ['Sm144',2.243934e-10], + ['Sm147',1.0928249999999999e-09], + ['Sm148',8.1961875e-10], + ['Sm149',1.0068561e-09], + ['Sm150',5.3694135e-10], + ['Sm152',1.9481427000000003e-09], + ['Sm154',1.6567226999999999e-09]]) +# Material Name: 9/16in Be disc +# S(a,b): c_Be (Not Implemented) +m6 = mcdc.material(nuclides=[ + ['Be9',0.11984], + ['Al27',2.4412e-05], + ['B10',2.0125228e-07], + ['B11',8.1414772e-07], + ['Bi209',2.6265e-06], + ['Br79',3.481824084e-09], + ['Br81',3.3875759160000003e-09], + ['C0',0.00010968], + ['Cd106',2.431734e-10], + ['Cd108',1.7344416e-10], + ['Cd110',2.4356404e-09], + ['Cd111',2.4991194e-09], + ['Cd112',4.70896988e-09], + ['Cd113',2.38817764e-09], + ['Cd114',5.61623128e-09], + ['Cd116',1.4672438400000001e-09], + ['Dy156',3.783136e-12], + ['Dy158',6.41782e-12], + ['Dy160',1.57337924e-10], + ['Dy161',1.276065284e-09], + ['Dy162',1.7209890999999998e-09], + ['Dy163',1.681874176e-09], + ['Dy164',1.9091325600000002e-09], + ['Fe54',1.4936897499999999e-06], + ['Fe56',2.34477347e-05], + ['Fe57',5.4151045e-07], + ['Fe58',7.20651e-08], + ['Gd152',1.3962200000000001e-11], + ['Gd154',1.5218798000000002e-10], + ['Gd155',1.0332028e-09], + ['Gd156',1.42903117e-09], + ['Gd157',1.09254215e-09], + ['Gd158',1.7341052400000002e-09], + ['Gd160',1.52606846e-09], + ['Mg24',7.131959634000001e-06], + ['Mg25',9.051466800000001e-07], + ['Mg26',9.96293686e-07], + ['Ni58',1.2733784145e-08], + ['Ni60',4.905030855e-09], + ['Ni61',2.13218295e-10], + ['Ni62',6.798332250000001e-10], + ['Ni64',1.7313348000000002e-10], + ['O16',0.00084676895289], + ['O17',3.2104711e-07], + ['Sm144',2.2487080000000002e-10], + ['Sm147',1.09515e-09], + ['Sm148',8.213625e-10], + ['Sm149',1.0089982e-09], + ['Sm150',5.380837e-10], + ['Sm152',1.9522874e-09], + ['Sm154',1.6602474e-09]]) +# Material Name: 1in Be disc +# S(a,b): c_Be (Not Implemented) +m7 = mcdc.material(nuclides=[ + ['Be9',0.12094], + ['Al27',2.4636e-05], + ['B10',2.0311535999999996e-07], + ['B11',8.216846399999999e-07], + ['Bi209',2.6507e-06], + ['Br79',3.5138069499999997e-09], + ['Br81',3.4186930500000005e-09], + ['C0',0.00011059], + ['Cd106',2.4540195e-10], + ['Cd108',1.7503368000000002e-10], + ['Cd110',2.4579617e-09], + ['Cd111',2.5220224500000003e-09], + ['Cd112',4.7521249900000004e-09], + ['Cd113',2.41006397e-09], + ['Cd114',5.667700940000001e-09], + ['Cd116',1.4806903200000002e-09], + ['Dy156',3.817855999999999e-12], + ['Dy158',6.47672e-12], + ['Dy160',1.58781904e-10], + ['Dy161',1.287776464e-09], + ['Dy162',1.7367835999999998e-09], + ['Dy163',1.697309696e-09], + ['Dy164',1.92665376e-09], + ['Fe54',1.5074255e-06], + ['Fe56',2.36633566e-05], + ['Fe57',5.464901e-07], + ['Fe58',7.27278e-08], + ['Gd152',1.40906e-11], + ['Gd154',1.5358754e-10], + ['Gd155',1.0427043999999999e-09], + ['Gd156',1.44217291e-09], + ['Gd157',1.10258945e-09], + ['Gd158',1.75005252e-09], + ['Gd160',1.54010258e-09], + ['Mg24',7.197488964e-06], + ['Mg25',9.134632799999999e-07], + ['Mg26',1.005447756e-06], + ['Ni58',1.2850876413e-08], + ['Ni60',4.950134587e-09], + ['Ni61',2.15178923e-10], + ['Ni62',6.86084565e-10], + ['Ni64',1.7472551200000002e-10], + ['O16',0.00085455600048], + ['O17',3.2399952e-07], + ['Sm144',2.2693748e-10], + ['Sm147',1.1052149999999999e-09], + ['Sm148',8.2891125e-10], + ['Sm149',1.01827142e-09], + ['Sm150',5.4302897e-10], + ['Sm152',1.9702299400000003e-09], + ['Sm154',1.6755059399999998e-09]]) +# Material Name: 1.5in Be disc +# S(a,b): c_Be (Not Implemented) +m8 = mcdc.material(nuclides=[ + ['Be9',0.12112], + ['Al27',2.4672e-05], + ['B10',2.0339284e-07], + ['B11',8.2280716e-07], + ['Bi209',2.6545e-06], + ['Br79',3.51887555e-09], + ['Br81',3.42362445e-09], + ['C0',0.00011084], + ['Cd106',2.4576299999999996e-10], + ['Cd108',1.7529120000000002e-10], + ['Cd110',2.4615780000000003e-09], + ['Cd111',2.5257330000000003e-09], + ['Cd112',4.7591166e-09], + ['Cd113',2.4136098000000002e-09], + ['Cd114',5.6760396e-09], + ['Cd116',1.4828688e-09], + ['Dy156',3.8234e-12], + ['Dy158',6.486125e-12], + ['Dy160',1.5901247500000002e-10], + ['Dy161',1.2896464750000001e-09], + ['Dy162',1.739305625e-09], + ['Dy163',1.6997744e-09], + ['Dy164',1.9294515000000003e-09], + ['Fe54',1.50958815e-06], + ['Fe56',2.3697305579999998e-05], + ['Fe57',5.4727413e-07], + ['Fe58',7.283213999999999e-08], + ['Gd152',1.4110800000000002e-11], + ['Gd154',1.5380772e-10], + ['Gd155',1.0441992e-09], + ['Gd156',1.44424038e-09], + ['Gd157',1.1041701e-09], + ['Gd158',1.75256136e-09], + ['Gd160',1.54231044e-09], + ['Mg24',7.207831545e-06], + ['Mg25',9.147758999999999e-07], + ['Mg26',1.006892555e-06], + ['Ni58',1.2869257175999998e-08], + ['Ni60',4.957214823999999e-09], + ['Ni61',2.1548669599999998e-10], + ['Ni62',6.8706588e-10], + ['Ni64',1.74975424e-10], + ['O16',0.00085578553431], + ['O17',3.2446569e-07], + ['Sm144',2.2726396e-10], + ['Sm147',1.1068049999999999e-09], + ['Sm148',8.3010375e-10], + ['Sm149',1.0197363399999999e-09], + ['Sm150',5.4381019e-10], + ['Sm152',1.9730643800000003e-09], + ['Sm154',1.67791638e-09]]) +# Material Name: 2in Be disc +# S(a,b): c_Be (Not Implemented) +m9 = mcdc.material(nuclides=[ + ['Be9',0.12073], + ['Al27',2.4594e-05], + ['B10',2.0275859999999997e-07], + ['B11',8.202413999999999e-07], + ['Bi209',2.6461e-06], + ['Br79',3.5077246299999997e-09], + ['Br81',3.41277537e-09], + ['C0',0.00011049], + ['Cd106',2.4497865e-10], + ['Cd108',1.7473176000000003e-10], + ['Cd110',2.4537219000000003e-09], + ['Cd111',2.5176721500000003e-09], + ['Cd112',4.743927930000001e-09], + ['Cd113',2.4059067900000004e-09], + ['Cd114',5.65792458e-09], + ['Cd116',1.4781362400000002e-09], + ['Dy156',3.811304e-12], + ['Dy158',6.465605e-12], + ['Dy160',1.58509411e-10], + ['Dy161',1.285566451e-09], + ['Dy162',1.7338030249999999e-09], + ['Dy163',1.694396864e-09], + ['Dy164',1.92334734e-09], + ['Fe54',1.5047952500000001e-06], + ['Fe56',2.3622067300000003e-05], + ['Fe57',5.4553655e-07], + ['Fe58',7.260090000000001e-08], + ['Gd152',1.40662e-11], + ['Gd154',1.5332158e-10], + ['Gd155',1.0408987999999998e-09], + ['Gd156',1.4396755699999998e-09], + ['Gd157',1.10068015e-09], + ['Gd158',1.74702204e-09], + ['Gd160',1.53743566e-09], + ['Mg24',7.185014706000001e-06], + ['Mg25',9.1188012e-07], + ['Mg26',1.0037051740000002e-06], + ['Ni58',1.2828411036e-08], + ['Ni60',4.941480964e-09], + ['Ni61',2.1480275599999999e-10], + ['Ni62',6.8488518e-10], + ['Ni64',1.7442006400000001e-10], + ['O16',0.0008530765614], + ['O17',3.234386e-07], + ['Sm144',2.2654632e-10], + ['Sm147',1.10331e-09], + ['Sm148',8.274825e-10], + ['Sm149',1.0165162799999999e-09], + ['Sm150',5.4209298e-10], + ['Sm152',1.96683396e-09], + ['Sm154',1.6726179599999998e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=3.816604, bc='interface') +s3 = mcdc.surface('plane-z', z=3.818382, bc='interface') +s4 = mcdc.surface('plane-z', z=7.632573, bc='interface') +s5 = mcdc.surface('plane-z', z=7.634351, bc='interface') +s6 = mcdc.surface('plane-z', z=10.177526, bc='interface') +s7 = mcdc.surface('plane-z', z=10.179304, bc='interface') +s8 = mcdc.surface('plane-z', z=10.496804, bc='interface') +s9 = mcdc.surface('plane-z', z=10.50163, bc='interface') +s10 = mcdc.surface('plane-z', z=14.31163, bc='interface') +s11 = mcdc.surface('plane-z', z=14.316456, bc='interface') +s12 = mcdc.surface('plane-z', z=19.396456, bc='interface') +s13 = mcdc.surface('plane-z', z=19.401282, bc='interface') +s14 = mcdc.surface('plane-z', z=21.941282, bc='interface') +s15 = mcdc.surface('plane-z', z=21.946108, bc='interface') +s16 = mcdc.surface('plane-z', z=23.216108, bc='interface') +s17 = mcdc.surface('plane-z', z=23.220934, bc='interface') +s18 = mcdc.surface('plane-z', z=24.649684, bc='vacuum') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.88492, bc='interface') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.885428, bc='interface') +s22 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.88546, bc='interface') +s23 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.885555, bc='interface') +s24 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.88603, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s24, fill=m2) +c2 = mcdc.cell(+s3 & -s4 & -s21, fill=m3) +c3 = mcdc.cell(+s5 & -s6 & -s20, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s23, fill=m4) +c5 = mcdc.cell(+s9 & -s10 & -s22, fill=m8) +c6 = mcdc.cell(+s11 & -s12 & -s22, fill=m9) +c7 = mcdc.cell(+s13 & -s14 & -s22, fill=m7) +c8 = mcdc.cell(+s15 & -s16 & -s22, fill=m5) +c9 = mcdc.cell(+s17 & -s18 & -s22, fill=m6) +c10 = mcdc.cell(+s2 & -s3 & -s24, fill=mvoid) +c11 = mcdc.cell(+s3 & -s4 & +s21 & -s24, fill=mvoid) +c12 = mcdc.cell(+s4 & -s5 & -s24, fill=mvoid) +c13 = mcdc.cell(+s5 & -s6 & +s20 & -s24, fill=mvoid) +c14 = mcdc.cell(+s6 & -s7 & -s24, fill=mvoid) +c15 = mcdc.cell(+s7 & -s8 & +s23 & -s24, fill=mvoid) +c16 = mcdc.cell(+s8 & -s9 & -s22, fill=mvoid) +c17 = mcdc.cell(+s10 & -s11 & -s22, fill=mvoid) +c18 = mcdc.cell(+s12 & -s13 & -s22, fill=mvoid) +c19 = mcdc.cell(+s14 & -s15 & -s22, fill=mvoid) +c20 = mcdc.cell(+s16 & -s17 & -s22, fill=mvoid) +c21 = mcdc.cell(+s8 & -s18 & +s22 & -s24, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Original Conditions (Some Not Implemented) +# energy_grid = nuclide +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-069/mcdc/heu-met-fast-069_case-2.py b/icsbep/openmc/heu-met-fast-069/mcdc/heu-met-fast-069_case-2.py new file mode 100644 index 0000000..3bb518a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/mcdc/heu-met-fast-069_case-2.py @@ -0,0 +1,50 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044736], + ['U238',0.0026745]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.12056]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-10.4775, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=14.12875, bc='vacuum') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=8.89, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s4, fill=m1) +c2 = mcdc.cell(+s2 & -s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-fast-069/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..e8d7bdb --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-1/generate_materials.py @@ -0,0 +1,221 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU part 2732" +mat.set_density('sum') +mat.add_nuclide('U234', 4.5765e-04) +mat.add_nuclide('U235', 4.4692e-02) +mat.add_nuclide('U236', 1.0030e-04) +mat.add_nuclide('U238', 2.6854e-03) +mat.add_element('Ag', 8.3658e-07) +mat.add_element('Ba', 4.1070e-10) +mat.add_element('Bi', 8.8522e-06) +mat.add_element('C', 4.6957e-06) +mat.add_element('Ca', 2.8145e-08) +mat.add_element('Cd', 5.0174e-08) +mat.add_element('Co', 9.5702e-07) +mat.add_element('Cr', 1.5186e-06) +mat.add_element('Cu', 4.4378e-06) +mat.add_element('K', 2.8851e-08) +mat.add_element('Li', 1.6251e-06) +mat.add_element('Mg', 1.3923e-06) +mat.add_element('Mn', 1.1498e-05) +mat.add_element('Mo', 5.8787e-08) +mat.add_element('Na', 1.3248e-05) +mat.add_element('Ni', 1.9220e-05) +mat.add_element('Sb', 3.5207e-06) +mat.add_element('Ti', 2.3559e-07) +mat.add_element('O', 1.4101e-05) +mat.add_element('N', 2.4160e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU part 2733" +mat.set_density('sum') +mat.add_nuclide('U234', 4.6267e-04) +mat.add_nuclide('U235', 4.4702e-02) +mat.add_nuclide('U236', 1.2424e-04) +mat.add_nuclide('U238', 2.6677e-03) +mat.add_element('Ag', 8.3696e-07) +mat.add_element('Ba', 4.1089e-10) +mat.add_element('Bi', 8.8562e-06) +mat.add_element('C', 4.6978e-06) +mat.add_element('Ca', 2.8158e-08) +mat.add_element('Cd', 5.0196e-08) +mat.add_element('Co', 9.5745e-07) +mat.add_element('Cr', 1.5193e-06) +mat.add_element('Cu', 4.4398e-06) +mat.add_element('K', 2.8864e-08) +mat.add_element('Li', 1.6259e-06) +mat.add_element('Mg', 1.3929e-06) +mat.add_element('Mn', 1.1503e-05) +mat.add_element('Mo', 5.8814e-08) +mat.add_element('Na', 1.3254e-05) +mat.add_element('Ni', 1.9228e-05) +mat.add_element('Sb', 3.5223e-06) +mat.add_element('Ti', 2.3570e-07) +mat.add_element('O', 1.4107e-05) +mat.add_element('N', 2.4171e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "HEU part 2734" +mat.set_density('sum') +mat.add_nuclide('U234', 4.5821e-04) +mat.add_nuclide('U235', 4.4751e-02) +mat.add_nuclide('U236', 1.1477e-04) +mat.add_nuclide('U238', 2.6697e-03) +mat.add_element('Ag', 8.3760e-07) +mat.add_element('Ba', 4.1120e-10) +mat.add_element('Bi', 8.8630e-06) +mat.add_element('C', 4.7015e-06) +mat.add_element('Ca', 2.8180e-08) +mat.add_element('Cd', 5.0235e-08) +mat.add_element('Co', 9.5819e-07) +mat.add_element('Cr', 1.5204e-06) +mat.add_element('Cu', 4.4432e-06) +mat.add_element('K', 2.8886e-08) +mat.add_element('Li', 1.6271e-06) +mat.add_element('Mg', 1.3940e-06) +mat.add_element('Mn', 1.1512e-05) +mat.add_element('Mo', 5.8859e-08) +mat.add_element('Na', 1.3264e-05) +mat.add_element('Ni', 1.9243e-05) +mat.add_element('Sb', 3.5250e-06) +mat.add_element('Ti', 2.3588e-07) +mat.add_element('O', 1.4118e-05) +mat.add_element('N', 2.4190e-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "HEU part 2768" +mat.set_density('sum') +mat.add_nuclide('U234', 4.4496e-04) +mat.add_nuclide('U235', 4.4855e-02) +mat.add_nuclide('U236', 1.2468e-04) +mat.add_nuclide('U238', 2.7009e-03) +mat.add_element('Ag', 8.3992e-07) +mat.add_element('Ba', 4.1234e-10) +mat.add_element('Bi', 8.8875e-06) +mat.add_element('C', 4.7145e-06) +mat.add_element('Ca', 2.8258e-08) +mat.add_element('Cd', 5.0374e-08) +mat.add_element('Co', 9.6084e-07) +mat.add_element('Cr', 1.5246e-06) +mat.add_element('Cu', 4.4555e-06) +mat.add_element('K', 2.8966e-08) +mat.add_element('Li', 1.6316e-06) +mat.add_element('Mg', 1.3979e-06) +mat.add_element('Mn', 1.1544e-05) +mat.add_element('Mo', 5.9022e-08) +mat.add_element('Na', 1.3301e-05) +mat.add_element('Ni', 1.9296e-05) +mat.add_element('Sb', 3.5347e-06) +mat.add_element('Ti', 2.3653e-07) +mat.add_element('O', 1.4157e-05) +mat.add_element('N', 2.4256e-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "0.5in Be disc" +mat.set_density('sum') +mat.add_element('Be', 1.1959e-01) +mat.add_element('Al', 2.4360e-05) +mat.add_element('B', 1.0133e-06) +mat.add_element('Bi', 2.6209e-06) +mat.add_element('Br', 6.8547e-09) +mat.add_element('C', 1.0944e-04) +mat.add_element('Cd', 1.9490e-08) +mat.add_element('Dy', 6.7412e-09) +mat.add_element('Fe', 2.5500e-05) +mat.add_element('Gd', 6.9662e-09) +mat.add_element('Mg', 9.0141e-06) +mat.add_element('Ni', 1.8665e-08) +mat.add_element('O', 8.4529e-04) +mat.add_element('Sm', 7.2855e-09) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "9/16in Be disc" +mat.set_density('sum') +mat.add_element('Be', 1.1984e-01) +mat.add_element('Al', 2.4412e-05) +mat.add_element('B', 1.0154e-06) +mat.add_element('Bi', 2.6265e-06) +mat.add_element('Br', 6.8694e-09) +mat.add_element('C', 1.0968e-04) +mat.add_element('Cd', 1.9532e-08) +mat.add_element('Dy', 6.7556e-09) +mat.add_element('Fe', 2.5555e-05) +mat.add_element('Gd', 6.9811e-09) +mat.add_element('Mg', 9.0334e-06) +mat.add_element('Ni', 1.8705e-08) +mat.add_element('O', 8.4709e-04) +mat.add_element('Sm', 7.3010e-09) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "1in Be disc" +mat.set_density('sum') +mat.add_element('Be', 1.2094e-01) +mat.add_element('Al', 2.4636e-05) +mat.add_element('B', 1.0248e-06) +mat.add_element('Bi', 2.6507e-06) +mat.add_element('Br', 6.9325e-09) +mat.add_element('C', 1.1059e-04) +mat.add_element('Cd', 1.9711e-08) +mat.add_element('Dy', 6.8176e-09) +mat.add_element('Fe', 2.5790e-05) +mat.add_element('Gd', 7.0453e-09) +mat.add_element('Mg', 9.1164e-06) +mat.add_element('Ni', 1.8877e-08) +mat.add_element('O', 8.5488e-04) +mat.add_element('Sm', 7.3681e-09) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "1.5in Be disc" +mat.set_density('sum') +mat.add_element('Be', 1.2112e-01) +mat.add_element('Al', 2.4672e-05) +mat.add_element('B', 1.0262e-06) +mat.add_element('Bi', 2.6545e-06) +mat.add_element('Br', 6.9425e-09) +mat.add_element('C', 1.1084e-04) +mat.add_element('Cd', 1.9740e-08) +mat.add_element('Dy', 6.8275e-09) +mat.add_element('Fe', 2.5827e-05) +mat.add_element('Gd', 7.0554e-09) +mat.add_element('Mg', 9.1295e-06) +mat.add_element('Ni', 1.8904e-08) +mat.add_element('O', 8.5611e-04) +mat.add_element('Sm', 7.3787e-09) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "2in Be disc" +mat.set_density('sum') +mat.add_element('Be', 1.2073e-01) +mat.add_element('Al', 2.4594e-05) +mat.add_element('B', 1.0230e-06) +mat.add_element('Bi', 2.6461e-06) +mat.add_element('Br', 6.9205e-09) +mat.add_element('C', 1.1049e-04) +mat.add_element('Cd', 1.9677e-08) +mat.add_element('Dy', 6.8059e-09) +mat.add_element('Fe', 2.5745e-05) +mat.add_element('Gd', 7.0331e-09) +mat.add_element('Mg', 9.1006e-06) +mat.add_element('Ni', 1.8844e-08) +mat.add_element('O', 8.5340e-04) +mat.add_element('Sm', 7.3554e-09) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-fast-069/openmc/case-1/geometry.xml new file mode 100644 index 0000000..6519d08 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-1/geometry.xml @@ -0,0 +1,63 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-fast-069/openmc/case-1/materials.xml new file mode 100644 index 0000000..503a75a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-1/materials.xml @@ -0,0 +1,566 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-fast-069/openmc/case-1/settings.xml new file mode 100644 index 0000000..c24263a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-1/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + nuclide + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-fast-069/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..00a0360 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-2/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.5958e-04) +mat.add_nuclide('U235', 4.4736e-02) +mat.add_nuclide('U236', 1.1523e-04) +mat.add_nuclide('U238', 2.6745e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2056e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-fast-069/openmc/case-2/geometry.xml new file mode 100644 index 0000000..17be15a --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-fast-069/openmc/case-2/materials.xml new file mode 100644 index 0000000..65dd3eb --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-2/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-fast-069/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-fast-069/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/heu-met-fast-069/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-1.py b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-1.py new file mode 100644 index 0000000..c02f9fd --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-1.py @@ -0,0 +1,182 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044918], + ['U238',0.002574]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.08538]]) +# Material Name: Cu +m3 = mcdc.material(nuclides=[ + ['Cu63',0.05724237000000001], + ['Cu65',0.025537630000000002]]) +# Material Name: Al 6061-T6 +m4 = mcdc.material(nuclides=[ + ['Si28',0.00031630168756000004], + ['Si29',1.6060897220000002e-05], + ['Si30',1.058741522e-05], + ['Fe54',5.8806545e-06], + ['Fe56',9.23136994e-05], + ['Fe57',2.1319259000000002e-06], + ['Fe58',2.837202e-07], + ['Cu63',4.80391965e-05], + ['Cu65',2.14318035e-05], + ['Mn55',2.1915e-05], + ['Mg24',0.0005214634599], + ['Mg25',6.6181098e-05], + ['Mg26',7.28454421e-05], + ['Cr50',3.35368825e-06], + ['Cr52',6.467253965e-05], + ['Cr53',7.33334685e-06], + ['Cr54',1.82542525e-06], + ['Zn64',1.5088797899999998e-05], + ['Zn66',8.509505099999999e-06], + ['Zn67',1.2397548e-06], + ['Zn68',5.6617514999999996e-06], + ['Zn70',1.871907e-07], + ['Ti46',2.074545e-06], + ['Ti47',1.8708623999999995e-06], + ['Ti48',1.8537631199999998e-05], + ['Ti49',1.3603986e-06], + ['Ti50',1.3025628e-06], + ['Al27',0.057816]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-5.7912, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=3.4972, bc='interface') +s4 = mcdc.surface('plane-z', z=9.8472, bc='interface') +s5 = mcdc.surface('plane-z', z=24.2744, bc='interface') +s6 = mcdc.surface('plane-z', z=28.30384, bc='interface') +s7 = mcdc.surface('plane-z', z=28.60356, bc='interface') +s8 = mcdc.surface('plane-z', z=32.633, bc='interface') +s9 = mcdc.surface('plane-z', z=36.66244, bc='interface') +s10 = mcdc.surface('plane-z', z=36.96216, bc='interface') +s11 = mcdc.surface('plane-z', z=40.9916, bc='interface') +s12 = mcdc.surface('plane-z', z=45.02104, bc='interface') +s13 = mcdc.surface('plane-z', z=45.32076, bc='interface') +s14 = mcdc.surface('plane-z', z=49.3502, bc='interface') +s15 = mcdc.surface('plane-z', z=53.37964, bc='interface') +s16 = mcdc.surface('plane-z', z=53.67936, bc='interface') +s17 = mcdc.surface('plane-z', z=57.7088, bc='interface') +s18 = mcdc.surface('plane-z', z=61.73824, bc='interface') +s19 = mcdc.surface('plane-z', z=62.03796, bc='interface') +s20 = mcdc.surface('plane-z', z=66.0674, bc='interface') +s21 = mcdc.surface('plane-z', z=70.09684, bc='interface') +s22 = mcdc.surface('plane-z', z=70.39656, bc='interface') +s23 = mcdc.surface('plane-z', z=74.426, bc='interface') +s24 = mcdc.surface('plane-z', z=78.45544, bc='interface') +s25 = mcdc.surface('plane-z', z=78.75516, bc='interface') +s26 = mcdc.surface('plane-z', z=82.7846, bc='interface') +s27 = mcdc.surface('plane-z', z=86.81404, bc='interface') +s28 = mcdc.surface('plane-z', z=87.11376, bc='interface') +s29 = mcdc.surface('plane-z', z=91.1432, bc='interface') +s30 = mcdc.surface('plane-z', z=95.17264, bc='interface') +s31 = mcdc.surface('plane-z', z=95.47236, bc='interface') +s32 = mcdc.surface('plane-z', z=99.5018, bc='interface') +s33 = mcdc.surface('plane-z', z=103.53124, bc='interface') +s34 = mcdc.surface('plane-z', z=103.83096, bc='interface') +s35 = mcdc.surface('plane-z', z=107.8604, bc='interface') +s36 = mcdc.surface('plane-z', z=108.6104, bc='interface') +s37 = mcdc.surface('plane-z', z=123.0376, bc='interface') +s38 = mcdc.surface('plane-z', z=123.9012, bc='vacuum') +s39 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.54, bc='interface') +s40 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.1496, bc='interface') +s41 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.175, bc='interface') +s42 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.7625, bc='interface') +s43 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.67, bc='interface') +s44 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.797, bc='interface') +s45 = mcdc.surface('plane-x', x=-27.94, bc='interface') +s46 = mcdc.surface('plane-x', x=27.94, bc='interface') +s47 = mcdc.surface('plane-y', y=-27.94, bc='interface') +s48 = mcdc.surface('plane-y', y=27.94, bc='interface') +s49 = mcdc.surface('plane-x', x=-44.1452, bc='vacuum') +s50 = mcdc.surface('plane-x', x=44.1452, bc='vacuum') +s51 = mcdc.surface('plane-y', y=-44.1452, bc='vacuum') +s52 = mcdc.surface('plane-y', y=44.1452, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s17 & -s39, fill=mvoid) +c2 = mcdc.cell(+s1 & -s17 & +s39 & -s40, fill=m4) +c3 = mcdc.cell(+s1 & -s17 & +s40 & -s41, fill=mvoid) +c4 = mcdc.cell(+s1 & -s2 & +s41 & +s49 & -s50 & +s51 & -s52, fill=mvoid) +c5 = mcdc.cell(+s2 & -s3 & +s41 & -s44, fill=mvoid) +c6 = mcdc.cell(+s2 & -s3 & +s44 & +s49 & -s50 & +s51 & -s52, fill=m3) +c7 = mcdc.cell(+s3 & -s4 & +s41 & -s42, fill=mvoid) +c8 = mcdc.cell(+s3 & -s4 & +s42 & -s43, fill=m4) +c9 = mcdc.cell(+s3 & -s4 & +s43 & -s44, fill=mvoid) +c10 = mcdc.cell(+s3 & -s4 & +s44 & +s49 & -s50 & +s51 & -s52, fill=m3) +c11 = mcdc.cell(+s4 & -s5 & +s41 & -s43, fill=m3) +c12 = mcdc.cell(+s4 & -s5 & +s43 & -s44, fill=mvoid) +c13 = mcdc.cell(+s4 & -s5 & +s44 & +s49 & -s50 & +s51 & -s52, fill=m3) +c14 = mcdc.cell(+s5 & -s6 & +s41 & -s43, fill=m2) +c15 = mcdc.cell(+s6 & -s7 & +s41 & -s43, fill=m1) +c16 = mcdc.cell(+s7 & -s8 & +s41 & -s43, fill=m2) +c17 = mcdc.cell(+s8 & -s9 & +s41 & -s43, fill=m2) +c18 = mcdc.cell(+s9 & -s10 & +s41 & -s43, fill=m1) +c19 = mcdc.cell(+s10 & -s11 & +s41 & -s43, fill=m2) +c20 = mcdc.cell(+s11 & -s12 & +s41 & -s43, fill=m2) +c21 = mcdc.cell(+s12 & -s13 & +s41 & -s43, fill=m1) +c22 = mcdc.cell(+s13 & -s14 & +s41 & -s43, fill=m2) +c23 = mcdc.cell(+s14 & -s15 & +s41 & -s43, fill=m2) +c24 = mcdc.cell(+s15 & -s16 & +s41 & -s43, fill=m1) +c25 = mcdc.cell(+s16 & -s17 & +s41 & -s43, fill=m2) +c26 = mcdc.cell(+s17 & -s18 & -s43, fill=m2) +c27 = mcdc.cell(+s18 & -s19 & -s43, fill=m1) +c28 = mcdc.cell(+s19 & -s20 & -s43, fill=m2) +c29 = mcdc.cell(+s20 & -s21 & -s43, fill=m2) +c30 = mcdc.cell(+s21 & -s22 & -s43, fill=m1) +c31 = mcdc.cell(+s22 & -s23 & -s43, fill=m2) +c32 = mcdc.cell(+s23 & -s24 & -s43, fill=m2) +c33 = mcdc.cell(+s24 & -s25 & -s43, fill=m1) +c34 = mcdc.cell(+s25 & -s26 & -s43, fill=m2) +c35 = mcdc.cell(+s26 & -s27 & -s43, fill=m2) +c36 = mcdc.cell(+s27 & -s28 & -s43, fill=m1) +c37 = mcdc.cell(+s28 & -s29 & -s43, fill=m2) +c38 = mcdc.cell(+s29 & -s30 & -s43, fill=m2) +c39 = mcdc.cell(+s30 & -s31 & -s43, fill=m1) +c40 = mcdc.cell(+s31 & -s32 & -s43, fill=m2) +c41 = mcdc.cell(+s32 & -s33 & -s43, fill=m2) +c42 = mcdc.cell(+s33 & -s34 & -s43, fill=m1) +c43 = mcdc.cell(+s34 & -s35 & -s43, fill=m2) +c44 = mcdc.cell(+s35 & -s36 & -s43, fill=mvoid) +c45 = mcdc.cell(+s36 & -s37 & -s44, fill=m3) +c46 = mcdc.cell(+s5 & -s36 & +s43 & -s44, fill=mvoid) +c47 = mcdc.cell(+s5 & -s37 & +s44 & +s49 & -s50 & +s51 & -s52, fill=m3) +c48 = mcdc.cell(+s37 & -s38 & +s45 & -s46 & +s47 & -s48, fill=mvoid) +c49 = mcdc.cell(+s37 & -s38 & +s49 & -s45 & +s51 & -s52, fill=m3) +c50 = mcdc.cell(+s37 & -s38 & +s46 & -s50 & +s51 & -s52, fill=m3) +c51 = mcdc.cell(+s37 & -s38 & +s45 & -s46 & +s51 & -s47, fill=m3) +c52 = mcdc.cell(+s37 & -s38 & +s45 & -s46 & +s48 & -s52, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[70.0,72.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-2.py b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-2.py new file mode 100644 index 0000000..1e22579 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-2.py @@ -0,0 +1,173 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044941], + ['U238',0.0025799]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.085821]]) +# Material Name: Cu +m3 = mcdc.material(nuclides=[ + ['Cu63',0.05724237000000001], + ['Cu65',0.025537630000000002]]) +# Material Name: Al 6061-T6 +m4 = mcdc.material(nuclides=[ + ['Si28',0.00031630168756000004], + ['Si29',1.6060897220000002e-05], + ['Si30',1.058741522e-05], + ['Fe54',5.8806545e-06], + ['Fe56',9.23136994e-05], + ['Fe57',2.1319259000000002e-06], + ['Fe58',2.837202e-07], + ['Cu63',4.80391965e-05], + ['Cu65',2.14318035e-05], + ['Mn55',2.1915e-05], + ['Mg24',0.0005214634599], + ['Mg25',6.6181098e-05], + ['Mg26',7.28454421e-05], + ['Cr50',3.35368825e-06], + ['Cr52',6.467253965e-05], + ['Cr53',7.33334685e-06], + ['Cr54',1.82542525e-06], + ['Zn64',1.5088797899999998e-05], + ['Zn66',8.509505099999999e-06], + ['Zn67',1.2397548e-06], + ['Zn68',5.6617514999999996e-06], + ['Zn70',1.871907e-07], + ['Ti46',2.074545e-06], + ['Ti47',1.8708623999999995e-06], + ['Ti48',1.8537631199999998e-05], + ['Ti49',1.3603986e-06], + ['Ti50',1.3025628e-06], + ['Al27',0.057816]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-5.7912, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=24.24384, bc='interface') +s4 = mcdc.surface('plane-z', z=30.59384, bc='interface') +s5 = mcdc.surface('plane-z', z=45.02104, bc='interface') +s6 = mcdc.surface('plane-z', z=48.04312, bc='interface') +s7 = mcdc.surface('plane-z', z=48.34284, bc='interface') +s8 = mcdc.surface('plane-z', z=51.36492, bc='interface') +s9 = mcdc.surface('plane-z', z=54.387, bc='interface') +s10 = mcdc.surface('plane-z', z=54.68672, bc='interface') +s11 = mcdc.surface('plane-z', z=57.7088, bc='interface') +s12 = mcdc.surface('plane-z', z=60.73088, bc='interface') +s13 = mcdc.surface('plane-z', z=61.0306, bc='interface') +s14 = mcdc.surface('plane-z', z=64.05268, bc='interface') +s15 = mcdc.surface('plane-z', z=67.07476, bc='interface') +s16 = mcdc.surface('plane-z', z=67.37448, bc='interface') +s17 = mcdc.surface('plane-z', z=70.39656, bc='interface') +s18 = mcdc.surface('plane-z', z=73.41864, bc='interface') +s19 = mcdc.surface('plane-z', z=73.71836, bc='interface') +s20 = mcdc.surface('plane-z', z=76.74044, bc='interface') +s21 = mcdc.surface('plane-z', z=79.76252, bc='interface') +s22 = mcdc.surface('plane-z', z=80.06224, bc='interface') +s23 = mcdc.surface('plane-z', z=83.08432, bc='interface') +s24 = mcdc.surface('plane-z', z=86.1064, bc='interface') +s25 = mcdc.surface('plane-z', z=86.40612, bc='interface') +s26 = mcdc.surface('plane-z', z=89.4282, bc='interface') +s27 = mcdc.surface('plane-z', z=92.45028, bc='interface') +s28 = mcdc.surface('plane-z', z=92.75, bc='interface') +s29 = mcdc.surface('plane-z', z=95.77208, bc='interface') +s30 = mcdc.surface('plane-z', z=98.79416, bc='interface') +s31 = mcdc.surface('plane-z', z=99.09388, bc='interface') +s32 = mcdc.surface('plane-z', z=102.11596, bc='interface') +s33 = mcdc.surface('plane-z', z=102.8954, bc='interface') +s34 = mcdc.surface('plane-z', z=117.3226, bc='interface') +s35 = mcdc.surface('plane-z', z=123.9012, bc='vacuum') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.54, bc='interface') +s37 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.1496, bc='interface') +s38 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.175, bc='interface') +s39 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.7625, bc='interface') +s40 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.67, bc='interface') +s41 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.797, bc='interface') +s42 = mcdc.surface('plane-x', x=-27.94, bc='interface') +s43 = mcdc.surface('plane-x', x=27.94, bc='interface') +s44 = mcdc.surface('plane-y', y=-27.94, bc='interface') +s45 = mcdc.surface('plane-y', y=27.94, bc='interface') +s46 = mcdc.surface('plane-x', x=-44.1452, bc='vacuum') +s47 = mcdc.surface('plane-x', x=44.1452, bc='vacuum') +s48 = mcdc.surface('plane-y', y=-44.1452, bc='vacuum') +s49 = mcdc.surface('plane-y', y=44.1452, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s11 & -s36, fill=mvoid) +c2 = mcdc.cell(+s1 & -s11 & +s36 & -s37, fill=m4) +c3 = mcdc.cell(+s1 & -s11 & +s37 & -s38, fill=mvoid) +c4 = mcdc.cell(+s1 & -s2 & +s46 & -s47 & +s48 & -s49, fill=mvoid) +c5 = mcdc.cell(+s2 & -s3 & +s38 & -s41, fill=mvoid) +c6 = mcdc.cell(+s3 & -s4 & +s38 & -s39, fill=mvoid) +c7 = mcdc.cell(+s3 & -s4 & +s39 & -s40, fill=m4) +c8 = mcdc.cell(+s3 & -s4 & +s40 & -s41, fill=mvoid) +c9 = mcdc.cell(+s4 & -s5 & +s38 & -s40, fill=m3) +c10 = mcdc.cell(+s4 & -s5 & +s40 & -s41, fill=mvoid) +c11 = mcdc.cell(+s5 & -s6 & +s38 & -s40, fill=m2) +c12 = mcdc.cell(+s6 & -s7 & +s38 & -s40, fill=m1) +c13 = mcdc.cell(+s7 & -s8 & +s38 & -s40, fill=m2) +c14 = mcdc.cell(+s8 & -s9 & +s38 & -s40, fill=m2) +c15 = mcdc.cell(+s9 & -s10 & +s38 & -s40, fill=m1) +c16 = mcdc.cell(+s10 & -s11 & +s38 & -s40, fill=m2) +c17 = mcdc.cell(+s11 & -s12 & -s40, fill=m2) +c18 = mcdc.cell(+s12 & -s13 & -s40, fill=m1) +c19 = mcdc.cell(+s13 & -s14 & -s40, fill=m2) +c20 = mcdc.cell(+s14 & -s15 & -s40, fill=m2) +c21 = mcdc.cell(+s15 & -s16 & -s40, fill=m1) +c22 = mcdc.cell(+s16 & -s17 & -s40, fill=m2) +c23 = mcdc.cell(+s17 & -s18 & -s40, fill=m2) +c24 = mcdc.cell(+s18 & -s19 & -s40, fill=m1) +c25 = mcdc.cell(+s19 & -s20 & -s40, fill=m2) +c26 = mcdc.cell(+s20 & -s21 & -s40, fill=m2) +c27 = mcdc.cell(+s21 & -s22 & -s40, fill=m1) +c28 = mcdc.cell(+s22 & -s23 & -s40, fill=m2) +c29 = mcdc.cell(+s23 & -s24 & -s40, fill=m2) +c30 = mcdc.cell(+s24 & -s25 & -s40, fill=m1) +c31 = mcdc.cell(+s25 & -s26 & -s40, fill=m2) +c32 = mcdc.cell(+s26 & -s27 & -s40, fill=m2) +c33 = mcdc.cell(+s27 & -s28 & -s40, fill=m1) +c34 = mcdc.cell(+s28 & -s29 & -s40, fill=m2) +c35 = mcdc.cell(+s29 & -s30 & -s40, fill=m2) +c36 = mcdc.cell(+s30 & -s31 & -s40, fill=m1) +c37 = mcdc.cell(+s31 & -s32 & -s40, fill=m2) +c38 = mcdc.cell(+s32 & -s33 & -s40, fill=mvoid) +c39 = mcdc.cell(+s33 & -s34 & -s41, fill=m3) +c40 = mcdc.cell(+s34 & -s35 & +s42 & -s43 & +s44 & -s45, fill=mvoid) +c41 = mcdc.cell(+s34 & -s35 & +s46 & -s42 & +s48 & -s49, fill=m3) +c42 = mcdc.cell(+s34 & -s35 & +s43 & -s47 & +s48 & -s49, fill=m3) +c43 = mcdc.cell(+s34 & -s35 & +s42 & -s43 & +s48 & -s44, fill=m3) +c44 = mcdc.cell(+s34 & -s35 & +s42 & -s43 & +s45 & -s49, fill=m3) +c45 = mcdc.cell(+s5 & -s33 & +s40 & -s41, fill=mvoid) +c46 = mcdc.cell(+s2 & -s34 & +s41 & +s46 & -s47 & +s48 & -s49, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[70.0,71.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-3.py b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-3.py new file mode 100644 index 0000000..f2d1198 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-3.py @@ -0,0 +1,173 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.04493], + ['U238',0.0025757]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.086431]]) +# Material Name: Cu +m3 = mcdc.material(nuclides=[ + ['Cu63',0.05724237000000001], + ['Cu65',0.025537630000000002]]) +# Material Name: Al 6061-T6 +m4 = mcdc.material(nuclides=[ + ['Si28',0.00031630168756000004], + ['Si29',1.6060897220000002e-05], + ['Si30',1.058741522e-05], + ['Fe54',5.8806545e-06], + ['Fe56',9.23136994e-05], + ['Fe57',2.1319259000000002e-06], + ['Fe58',2.837202e-07], + ['Cu63',4.80391965e-05], + ['Cu65',2.14318035e-05], + ['Mn55',2.1915e-05], + ['Mg24',0.0005214634599], + ['Mg25',6.6181098e-05], + ['Mg26',7.28454421e-05], + ['Cr50',3.35368825e-06], + ['Cr52',6.467253965e-05], + ['Cr53',7.33334685e-06], + ['Cr54',1.82542525e-06], + ['Zn64',1.5088797899999998e-05], + ['Zn66',8.509505099999999e-06], + ['Zn67',1.2397548e-06], + ['Zn68',5.6617514999999996e-06], + ['Zn70',1.871907e-07], + ['Ti46',2.074545e-06], + ['Ti47',1.8708623999999995e-06], + ['Ti48',1.8537631199999998e-05], + ['Ti49',1.3603986e-06], + ['Ti50',1.3025628e-06], + ['Al27',0.057816]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-5.7912, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=19.61496, bc='interface') +s4 = mcdc.surface('plane-z', z=25.96496, bc='interface') +s5 = mcdc.surface('plane-z', z=40.39216, bc='interface') +s6 = mcdc.surface('plane-z', z=42.40688, bc='interface') +s7 = mcdc.surface('plane-z', z=42.7066, bc='interface') +s8 = mcdc.surface('plane-z', z=44.72132, bc='interface') +s9 = mcdc.surface('plane-z', z=46.73604, bc='interface') +s10 = mcdc.surface('plane-z', z=47.03576, bc='interface') +s11 = mcdc.surface('plane-z', z=49.05048, bc='interface') +s12 = mcdc.surface('plane-z', z=51.0652, bc='interface') +s13 = mcdc.surface('plane-z', z=51.36492, bc='interface') +s14 = mcdc.surface('plane-z', z=53.37964, bc='interface') +s15 = mcdc.surface('plane-z', z=55.39436, bc='interface') +s16 = mcdc.surface('plane-z', z=55.69408, bc='interface') +s17 = mcdc.surface('plane-z', z=57.7088, bc='interface') +s18 = mcdc.surface('plane-z', z=59.72352, bc='interface') +s19 = mcdc.surface('plane-z', z=60.02324, bc='interface') +s20 = mcdc.surface('plane-z', z=62.03796, bc='interface') +s21 = mcdc.surface('plane-z', z=64.05268, bc='interface') +s22 = mcdc.surface('plane-z', z=64.3524, bc='interface') +s23 = mcdc.surface('plane-z', z=66.36712, bc='interface') +s24 = mcdc.surface('plane-z', z=68.38184, bc='interface') +s25 = mcdc.surface('plane-z', z=68.68156, bc='interface') +s26 = mcdc.surface('plane-z', z=70.69628, bc='interface') +s27 = mcdc.surface('plane-z', z=72.711, bc='interface') +s28 = mcdc.surface('plane-z', z=73.01072, bc='interface') +s29 = mcdc.surface('plane-z', z=75.02544, bc='interface') +s30 = mcdc.surface('plane-z', z=77.04016, bc='interface') +s31 = mcdc.surface('plane-z', z=77.33988, bc='interface') +s32 = mcdc.surface('plane-z', z=79.3546, bc='interface') +s33 = mcdc.surface('plane-z', z=79.59725, bc='interface') +s34 = mcdc.surface('plane-z', z=94.02445, bc='interface') +s35 = mcdc.surface('plane-z', z=123.9012, bc='vacuum') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.54, bc='interface') +s37 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.1496, bc='interface') +s38 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.175, bc='interface') +s39 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.7625, bc='interface') +s40 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.05, bc='interface') +s41 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.67, bc='interface') +s42 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.797, bc='interface') +s43 = mcdc.surface('plane-x', x=-44.1452, bc='vacuum') +s44 = mcdc.surface('plane-x', x=-27.94, bc='interface') +s45 = mcdc.surface('plane-x', x=27.94, bc='interface') +s46 = mcdc.surface('plane-x', x=44.1452, bc='vacuum') +s47 = mcdc.surface('plane-y', y=-44.1452, bc='vacuum') +s48 = mcdc.surface('plane-y', y=-27.94, bc='interface') +s49 = mcdc.surface('plane-y', y=27.94, bc='interface') +s50 = mcdc.surface('plane-y', y=44.1452, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s17 & -s36, fill=mvoid) +c2 = mcdc.cell(+s1 & -s17 & +s36 & -s37, fill=m4) +c3 = mcdc.cell(+s1 & -s17 & +s37 & -s38, fill=mvoid) +c4 = mcdc.cell(+s1 & -s2 & +s38 & +s43 & -s46 & +s47 & -s50, fill=mvoid) +c5 = mcdc.cell(+s2 & -s3 & +s38 & -s41, fill=mvoid) +c6 = mcdc.cell(+s3 & -s4 & +s38 & -s39, fill=mvoid) +c7 = mcdc.cell(+s3 & -s4 & +s39 & -s41, fill=m4) +c8 = mcdc.cell(+s4 & -s5 & +s38 & -s41, fill=m3) +c9 = mcdc.cell(+s5 & -s6 & +s38 & -s41, fill=m2) +c10 = mcdc.cell(+s6 & -s7 & +s38 & -s40, fill=m1) +c11 = mcdc.cell(+s6 & -s7 & +s40 & -s41, fill=mvoid) +c12 = mcdc.cell(+s7 & -s8 & +s38 & -s41, fill=m2) +c13 = mcdc.cell(+s8 & -s9 & +s38 & -s41, fill=m2) +c14 = mcdc.cell(+s9 & -s10 & +s38 & -s41, fill=m1) +c15 = mcdc.cell(+s10 & -s11 & +s38 & -s41, fill=m2) +c16 = mcdc.cell(+s11 & -s12 & +s38 & -s41, fill=m2) +c17 = mcdc.cell(+s12 & -s13 & +s38 & -s41, fill=m1) +c18 = mcdc.cell(+s13 & -s14 & +s38 & -s41, fill=m2) +c19 = mcdc.cell(+s14 & -s15 & +s38 & -s41, fill=m2) +c20 = mcdc.cell(+s15 & -s16 & +s38 & -s41, fill=m1) +c21 = mcdc.cell(+s16 & -s17 & +s38 & -s41, fill=m2) +c22 = mcdc.cell(+s17 & -s18 & -s41, fill=m2) +c23 = mcdc.cell(+s18 & -s19 & -s41, fill=m1) +c24 = mcdc.cell(+s19 & -s20 & -s41, fill=m2) +c25 = mcdc.cell(+s20 & -s21 & -s41, fill=m2) +c26 = mcdc.cell(+s21 & -s22 & -s41, fill=m1) +c27 = mcdc.cell(+s22 & -s23 & -s41, fill=m2) +c28 = mcdc.cell(+s23 & -s24 & -s41, fill=m2) +c29 = mcdc.cell(+s24 & -s25 & -s41, fill=m1) +c30 = mcdc.cell(+s25 & -s26 & -s41, fill=m2) +c31 = mcdc.cell(+s26 & -s27 & -s41, fill=m2) +c32 = mcdc.cell(+s27 & -s28 & -s41, fill=m1) +c33 = mcdc.cell(+s28 & -s29 & -s41, fill=m2) +c34 = mcdc.cell(+s29 & -s30 & -s41, fill=m2) +c35 = mcdc.cell(+s30 & -s31 & -s41, fill=m1) +c36 = mcdc.cell(+s31 & -s32 & -s41, fill=m2) +c37 = mcdc.cell(+s32 & -s33 & -s41, fill=mvoid) +c38 = mcdc.cell(+s33 & -s34 & -s42, fill=m3) +c39 = mcdc.cell(+s34 & -s35 & +s44 & -s45 & +s48 & -s49, fill=mvoid) +c40 = mcdc.cell(+s34 & -s35 & +s43 & -s44 & +s47 & -s50, fill=m3) +c41 = mcdc.cell(+s34 & -s35 & +s45 & -s46 & +s47 & -s50, fill=m3) +c42 = mcdc.cell(+s34 & -s35 & +s44 & -s45 & +s47 & -s48, fill=m3) +c43 = mcdc.cell(+s34 & -s35 & +s44 & -s45 & +s49 & -s50, fill=m3) +c44 = mcdc.cell(+s2 & -s33 & +s41 & -s42, fill=mvoid) +c45 = mcdc.cell(+s2 & -s34 & +s42 & +s43 & -s46 & +s47 & -s50, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-0.5,0.5], y=[-0.5,0.5], z=[57.2,57.7], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-4.py b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-4.py new file mode 100644 index 0000000..45b4fcb --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/mcdc/heu-met-inter-006_case-4.py @@ -0,0 +1,173 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.044949], + ['U238',0.0025779]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.086552]]) +# Material Name: Cu +m3 = mcdc.material(nuclides=[ + ['Cu63',0.05724237000000001], + ['Cu65',0.025537630000000002]]) +# Material Name: Al 6061-T6 +m4 = mcdc.material(nuclides=[ + ['Si28',0.00031630168756000004], + ['Si29',1.6060897220000002e-05], + ['Si30',1.058741522e-05], + ['Fe54',5.8806545e-06], + ['Fe56',9.23136994e-05], + ['Fe57',2.1319259000000002e-06], + ['Fe58',2.837202e-07], + ['Cu63',4.80391965e-05], + ['Cu65',2.14318035e-05], + ['Mn55',2.1915e-05], + ['Mg24',0.0005214634599], + ['Mg25',6.6181098e-05], + ['Mg26',7.28454421e-05], + ['Cr50',3.35368825e-06], + ['Cr52',6.467253965e-05], + ['Cr53',7.33334685e-06], + ['Cr54',1.82542525e-06], + ['Zn64',1.5088797899999998e-05], + ['Zn66',8.509505099999999e-06], + ['Zn67',1.2397548e-06], + ['Zn68',5.6617514999999996e-06], + ['Zn70',1.871907e-07], + ['Ti46',2.074545e-06], + ['Ti47',1.8708623999999995e-06], + ['Ti48',1.8537631199999998e-05], + ['Ti49',1.3603986e-06], + ['Ti50',1.3025628e-06], + ['Al27',0.057816]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-5.7912, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=29.98828, bc='interface') +s4 = mcdc.surface('plane-z', z=36.33828, bc='interface') +s5 = mcdc.surface('plane-z', z=50.76548, bc='interface') +s6 = mcdc.surface('plane-z', z=51.77284, bc='interface') +s7 = mcdc.surface('plane-z', z=52.07256, bc='interface') +s8 = mcdc.surface('plane-z', z=53.07992, bc='interface') +s9 = mcdc.surface('plane-z', z=54.08728, bc='interface') +s10 = mcdc.surface('plane-z', z=54.387, bc='interface') +s11 = mcdc.surface('plane-z', z=55.39436, bc='interface') +s12 = mcdc.surface('plane-z', z=56.40172, bc='interface') +s13 = mcdc.surface('plane-z', z=56.70144, bc='interface') +s14 = mcdc.surface('plane-z', z=57.7088, bc='interface') +s15 = mcdc.surface('plane-z', z=58.71616, bc='interface') +s16 = mcdc.surface('plane-z', z=59.01588, bc='interface') +s17 = mcdc.surface('plane-z', z=60.02324, bc='interface') +s18 = mcdc.surface('plane-z', z=61.0306, bc='interface') +s19 = mcdc.surface('plane-z', z=61.33032, bc='interface') +s20 = mcdc.surface('plane-z', z=62.33768, bc='interface') +s21 = mcdc.surface('plane-z', z=63.34504, bc='interface') +s22 = mcdc.surface('plane-z', z=63.64476, bc='interface') +s23 = mcdc.surface('plane-z', z=64.65212, bc='interface') +s24 = mcdc.surface('plane-z', z=65.65948, bc='interface') +s25 = mcdc.surface('plane-z', z=65.9592, bc='interface') +s26 = mcdc.surface('plane-z', z=66.96656, bc='interface') +s27 = mcdc.surface('plane-z', z=67.97392, bc='interface') +s28 = mcdc.surface('plane-z', z=68.27364, bc='interface') +s29 = mcdc.surface('plane-z', z=69.281, bc='interface') +s30 = mcdc.surface('plane-z', z=70.28836, bc='interface') +s31 = mcdc.surface('plane-z', z=70.58808, bc='interface') +s32 = mcdc.surface('plane-z', z=71.59544, bc='interface') +s33 = mcdc.surface('plane-z', z=71.83755, bc='interface') +s34 = mcdc.surface('plane-z', z=86.26475, bc='interface') +s35 = mcdc.surface('plane-z', z=123.9012, bc='vacuum') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.54, bc='interface') +s37 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.1496, bc='interface') +s38 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.175, bc='interface') +s39 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.7625, bc='interface') +s40 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.05, bc='interface') +s41 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.67, bc='interface') +s42 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.797, bc='interface') +s43 = mcdc.surface('plane-x', x=-44.1452, bc='vacuum') +s44 = mcdc.surface('plane-x', x=-27.94, bc='interface') +s45 = mcdc.surface('plane-x', x=27.94, bc='interface') +s46 = mcdc.surface('plane-x', x=44.1452, bc='vacuum') +s47 = mcdc.surface('plane-y', y=-44.1452, bc='vacuum') +s48 = mcdc.surface('plane-y', y=-27.94, bc='interface') +s49 = mcdc.surface('plane-y', y=27.94, bc='interface') +s50 = mcdc.surface('plane-y', y=44.1452, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s14 & -s36, fill=mvoid) +c2 = mcdc.cell(+s1 & -s14 & +s36 & -s37, fill=m4) +c3 = mcdc.cell(+s1 & -s14 & +s37 & -s38, fill=mvoid) +c4 = mcdc.cell(+s1 & -s2 & +s38 & +s43 & -s46 & +s47 & -s50, fill=mvoid) +c5 = mcdc.cell(+s2 & -s3 & +s38 & -s41, fill=mvoid) +c6 = mcdc.cell(+s3 & -s4 & +s38 & -s39, fill=mvoid) +c7 = mcdc.cell(+s3 & -s4 & +s39 & -s41, fill=m4) +c8 = mcdc.cell(+s4 & -s5 & +s38 & -s41, fill=m3) +c9 = mcdc.cell(+s5 & -s6 & +s38 & -s41, fill=m2) +c10 = mcdc.cell(+s6 & -s7 & +s38 & -s40, fill=m1) +c11 = mcdc.cell(+s6 & -s7 & +s40 & -s41, fill=mvoid) +c12 = mcdc.cell(+s7 & -s8 & +s38 & -s41, fill=m2) +c13 = mcdc.cell(+s8 & -s9 & +s38 & -s41, fill=m2) +c14 = mcdc.cell(+s9 & -s10 & +s38 & -s41, fill=m1) +c15 = mcdc.cell(+s10 & -s11 & +s38 & -s41, fill=m2) +c16 = mcdc.cell(+s11 & -s12 & +s38 & -s41, fill=m2) +c17 = mcdc.cell(+s12 & -s13 & +s38 & -s41, fill=m1) +c18 = mcdc.cell(+s13 & -s14 & +s38 & -s41, fill=m2) +c19 = mcdc.cell(+s14 & -s15 & -s41, fill=m2) +c20 = mcdc.cell(+s15 & -s16 & -s41, fill=m1) +c21 = mcdc.cell(+s16 & -s17 & -s41, fill=m2) +c22 = mcdc.cell(+s17 & -s18 & -s41, fill=m2) +c23 = mcdc.cell(+s18 & -s19 & -s41, fill=m1) +c24 = mcdc.cell(+s19 & -s20 & -s41, fill=m2) +c25 = mcdc.cell(+s20 & -s21 & -s41, fill=m2) +c26 = mcdc.cell(+s21 & -s22 & -s41, fill=m1) +c27 = mcdc.cell(+s22 & -s23 & -s41, fill=m2) +c28 = mcdc.cell(+s23 & -s24 & -s41, fill=m2) +c29 = mcdc.cell(+s24 & -s25 & -s41, fill=m1) +c30 = mcdc.cell(+s25 & -s26 & -s41, fill=m2) +c31 = mcdc.cell(+s26 & -s27 & -s41, fill=m2) +c32 = mcdc.cell(+s27 & -s28 & -s41, fill=m1) +c33 = mcdc.cell(+s28 & -s29 & -s41, fill=m2) +c34 = mcdc.cell(+s29 & -s30 & -s41, fill=m2) +c35 = mcdc.cell(+s30 & -s31 & -s41, fill=m1) +c36 = mcdc.cell(+s31 & -s32 & -s41, fill=m2) +c37 = mcdc.cell(+s32 & -s33 & -s41, fill=mvoid) +c38 = mcdc.cell(+s33 & -s34 & -s42, fill=m3) +c39 = mcdc.cell(+s34 & -s35 & +s44 & -s45 & +s48 & -s49, fill=mvoid) +c40 = mcdc.cell(+s34 & -s35 & +s43 & -s44 & +s47 & -s50, fill=m3) +c41 = mcdc.cell(+s34 & -s35 & +s45 & -s46 & +s47 & -s50, fill=m3) +c42 = mcdc.cell(+s34 & -s35 & +s44 & -s45 & +s47 & -s48, fill=m3) +c43 = mcdc.cell(+s34 & -s35 & +s44 & -s45 & +s49 & -s50, fill=m3) +c44 = mcdc.cell(+s2 & -s33 & +s41 & -s42, fill=mvoid) +c45 = mcdc.cell(+s2 & -s34 & +s42 & +s43 & -s46 & +s47 & -s50, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-0.5,0.5], y=[-0.5,0.5], z=[57.2,57.7], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-met-inter-006/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..70b715a --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-1/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9483e-04) +mat.add_nuclide('U235', 4.4918e-02) +mat.add_nuclide('U236', 1.5917e-04) +mat.add_nuclide('U238', 2.5740e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.5380e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cu" +mat.set_density('sum') +mat.add_element('Cu', 8.2780e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Al 6061-T6" +mat.set_density('sum') +mat.add_element('Si', 3.4295e-04) +mat.add_element('Fe', 1.0061e-04) +mat.add_element('Cu', 6.9471e-05) +mat.add_element('Mn', 2.1915e-05) +mat.add_element('Mg', 6.6049e-04) +mat.add_element('Cr', 7.7185e-05) +mat.add_element('Zn', 3.0687e-05) +mat.add_element('Ti', 2.5146e-05) +mat.add_element('Al', 5.7816e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-1/geometry.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-1/geometry.xml new file mode 100644 index 0000000..bcfd733 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-1/geometry.xml @@ -0,0 +1,148 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-1/materials.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-1/materials.xml new file mode 100644 index 0000000..5778e93 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-1/materials.xml @@ -0,0 +1,51 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-1/plots.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-1/plots.xml new file mode 100644 index 0000000..2a6abc8 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-1/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 50. + 90. 150. + 2000 2000 + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-1/settings.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-1/settings.xml new file mode 100644 index 0000000..8f59fde --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1. -1. 70. 1. 1. 72. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-met-inter-006/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..daa1a5f --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-2/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9576e-04) +mat.add_nuclide('U235', 4.4941e-02) +mat.add_nuclide('U236', 1.5931e-04) +mat.add_nuclide('U238', 2.5799e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.5821e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cu" +mat.set_density('sum') +mat.add_element('Cu', 8.2780e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Al 6061-T6" +mat.set_density('sum') +mat.add_element('Si', 3.4295e-04) +mat.add_element('Fe', 1.0061e-04) +mat.add_element('Cu', 6.9471e-05) +mat.add_element('Mn', 2.1915e-05) +mat.add_element('Mg', 6.6049e-04) +mat.add_element('Cr', 7.7185e-05) +mat.add_element('Zn', 3.0687e-05) +mat.add_element('Ti', 2.5146e-05) +mat.add_element('Al', 5.7816e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-2/geometry.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-2/geometry.xml new file mode 100644 index 0000000..1aea23b --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-2/geometry.xml @@ -0,0 +1,134 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-2/materials.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-2/materials.xml new file mode 100644 index 0000000..d5ee292 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-2/materials.xml @@ -0,0 +1,51 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-2/plots.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-2/plots.xml new file mode 100644 index 0000000..2a6abc8 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-2/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 50. + 90. 150. + 2000 2000 + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-2/settings.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-2/settings.xml new file mode 100644 index 0000000..3793372 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1. -1. 70. 1. 1. 71. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-met-inter-006/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..6b6bbe0 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-3/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9568e-04) +mat.add_nuclide('U235', 4.4930e-02) +mat.add_nuclide('U236', 1.5647e-04) +mat.add_nuclide('U238', 2.5757e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.6431e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cu" +mat.set_density('sum') +mat.add_element('Cu', 8.2780e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Al 6061-T6" +mat.set_density('sum') +mat.add_element('Si', 3.4295e-04) +mat.add_element('Fe', 1.0061e-04) +mat.add_element('Cu', 6.9471e-05) +mat.add_element('Mn', 2.1915e-05) +mat.add_element('Mg', 6.6049e-04) +mat.add_element('Cr', 7.7185e-05) +mat.add_element('Zn', 3.0687e-05) +mat.add_element('Ti', 2.5146e-05) +mat.add_element('Al', 5.7816e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-3/geometry.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-3/geometry.xml new file mode 100644 index 0000000..7fab5c4 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-3/geometry.xml @@ -0,0 +1,134 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-3/materials.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-3/materials.xml new file mode 100644 index 0000000..510366a --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-3/materials.xml @@ -0,0 +1,51 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-3/plots.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-3/plots.xml new file mode 100644 index 0000000..2a6abc8 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-3/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 50. + 90. 150. + 2000 2000 + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-3/settings.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-3/settings.xml new file mode 100644 index 0000000..2e878a9 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -.5 -.5 57.2 .5 .5 57.7 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-met-inter-006/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..317ccc9 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-4/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9591e-04) +mat.add_nuclide('U235', 4.4949e-02) +mat.add_nuclide('U236', 1.5651e-04) +mat.add_nuclide('U238', 2.5779e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 8.6552e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cu" +mat.set_density('sum') +mat.add_element('Cu', 8.2780e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Al 6061-T6" +mat.set_density('sum') +mat.add_element('Si', 3.4295e-04) +mat.add_element('Fe', 1.0061e-04) +mat.add_element('Cu', 6.9471e-05) +mat.add_element('Mn', 2.1915e-05) +mat.add_element('Mg', 6.6049e-04) +mat.add_element('Cr', 7.7185e-05) +mat.add_element('Zn', 3.0687e-05) +mat.add_element('Ti', 2.5146e-05) +mat.add_element('Al', 5.7816e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-4/geometry.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-4/geometry.xml new file mode 100644 index 0000000..8c542c5 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-4/geometry.xml @@ -0,0 +1,134 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-4/materials.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-4/materials.xml new file mode 100644 index 0000000..2a2655e --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-4/materials.xml @@ -0,0 +1,51 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-4/plots.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-4/plots.xml new file mode 100644 index 0000000..2a6abc8 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-4/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 50. + 90. 150. + 2000 2000 + + + diff --git a/icsbep/openmc/heu-met-inter-006/openmc/case-4/settings.xml b/icsbep/openmc/heu-met-inter-006/openmc/case-4/settings.xml new file mode 100644 index 0000000..2e878a9 --- /dev/null +++ b/icsbep/openmc/heu-met-inter-006/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -.5 -.5 57.2 .5 .5 57.7 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-1.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-1.py new file mode 100644 index 0000000..57f81f2 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-1.py @@ -0,0 +1,87 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034777], + ['U238',1.9798e-05], + ['O16',0.035023720976999996], + ['O17',1.3279023e-05], + ['N14',0.00092307], + ['H1',0.06322]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['C0',0.00026231], + ['Si28',0.00126981823424], + ['Si29',6.447774688e-05], + ['Si30',4.250401888e-05], + ['P31',3.853e-05], + ['S32',2.6879422086800002e-05], + ['S33',2.1174450580000004e-07], + ['S34',1.1867098918000002e-06], + ['S36',4.1235156e-09], + ['Cr50',0.0007379982500000001], + ['Cr52',0.01423156165], + ['Cr53',0.00161374485], + ['Cr54',0.00040169525], + ['Mn55',0.0011209], + ['Fe54',0.0034983494], + ['Fe56',0.054916604079999994], + ['Fe57',0.0012682638800000001], + ['Fe58',0.00016878264000000002], + ['Ni58',0.0051329982599999996], + ['Ni60',0.00197722174], + ['Ni61',8.594846e-05], + ['Ni62',0.00027404130000000004], + ['Ni64',6.979024e-05], + ['Mo100',8.727018719999999e-07], + ['Mo92',1.312008387e-06], + ['Mo94',8.228152809999998e-07], + ['Mo95',1.4216334990000002e-06], + ['Mo96',1.4932838989999995e-06], + ['Mo97',8.58192666e-07], + ['Mo98',2.1756643959999998e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.96, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.28, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=31.2, bc='interface') +s6 = mcdc.surface('plane-z', z=41.6, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-10.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-10.py new file mode 100644 index 0000000..3497d5c --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-10.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00015266], + ['U238',8.6908e-06], + ['O16',0.034088075721], + ['O17',1.2924278999999998e-05], + ['N14',0.00039433], + ['H1',0.065247]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=25.345, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=25.665, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=20.48, bc='interface') +s6 = mcdc.surface('plane-z', z=30.9, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-2.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-2.py new file mode 100644 index 0000000..a990378 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-2.py @@ -0,0 +1,87 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00082771], + ['U238',4.712e-05], + ['O16',0.037120925835], + ['O17',1.4074165e-05], + ['N14',0.002102], + ['H1',0.058433]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['C0',0.00026231], + ['Si28',0.00126981823424], + ['Si29',6.447774688e-05], + ['Si30',4.250401888e-05], + ['P31',3.853e-05], + ['S32',2.6879422086800002e-05], + ['S33',2.1174450580000004e-07], + ['S34',1.1867098918000002e-06], + ['S36',4.1235156e-09], + ['Cr50',0.0007379982500000001], + ['Cr52',0.01423156165], + ['Cr53',0.00161374485], + ['Cr54',0.00040169525], + ['Mn55',0.0011209], + ['Fe54',0.0034983494], + ['Fe56',0.054916604079999994], + ['Fe57',0.0012682638800000001], + ['Fe58',0.00016878264000000002], + ['Ni58',0.0051329982599999996], + ['Ni60',0.00197722174], + ['Ni61',8.594846e-05], + ['Ni62',0.00027404130000000004], + ['Ni64',6.979024e-05], + ['Mo100',8.727018719999999e-07], + ['Mo92',1.312008387e-06], + ['Mo94',8.228152809999998e-07], + ['Mo95',1.4216334990000002e-06], + ['Mo96',1.4932838989999995e-06], + ['Mo97',8.58192666e-07], + ['Mo98',2.1756643959999998e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.96, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.28, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=28.93, bc='interface') +s6 = mcdc.surface('plane-z', z=41.6, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-3.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-3.py new file mode 100644 index 0000000..e782ed3 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-3.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034118], + ['U238',1.9423e-05], + ['O16',0.035019722493], + ['O17',1.3277507000000002e-05], + ['N14',0.00090231], + ['H1',0.063359]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.005, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.325, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=33.55, bc='interface') +s6 = mcdc.surface('plane-z', z=41.9, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-4.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-4.py new file mode 100644 index 0000000..f04a8f6 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-4.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00085392], + ['U238',4.861299999999999e-05], + ['O16',0.037237881492], + ['O17',1.4118507999999999e-05], + ['N14',0.0021624], + ['H1',0.058196]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.005, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.325, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=30.91, bc='interface') +s6 = mcdc.surface('plane-z', z=41.9, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-5.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-5.py new file mode 100644 index 0000000..66e5548 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-5.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00013103], + ['U238',7.4595e-06], + ['O16',0.033990112863], + ['O17',1.2887136999999999e-05], + ['N14',0.00034432], + ['H1',0.065441]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.505, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.825, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=39.48, bc='interface') +s6 = mcdc.surface('plane-z', z=49.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-6.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-6.py new file mode 100644 index 0000000..15c7d19 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-6.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0001424], + ['U238',8.1064e-06], + ['O16',0.03404409239699999], + ['O17',1.2907602999999996e-05], + ['N14',0.00037412], + ['H1',0.065327]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.505, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.825, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=36.67, bc='interface') +s6 = mcdc.surface('plane-z', z=49.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-7.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-7.py new file mode 100644 index 0000000..9e25a5f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-7.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.000328], + ['U238',1.8673e-05], + ['O16',0.034931755844999995], + ['O17',1.3244155e-05], + ['N14',0.00087645], + ['H1',0.063397]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.505, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.825, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=23.96, bc='interface') +s6 = mcdc.surface('plane-z', z=49.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-8.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-8.py new file mode 100644 index 0000000..7fe37c2 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-8.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034777], + ['U238',1.9798e-05], + ['O16',0.035023720976999996], + ['O17',1.3279023e-05], + ['N14',0.00092307], + ['H1',0.06322]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.505, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.825, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=23.67, bc='interface') +s6 = mcdc.surface('plane-z', z=49.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-9.py b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-9.py new file mode 100644 index 0000000..3330e70 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/mcdc/heu-sol-therm-001_case-9.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00085392], + ['U238',4.861299999999999e-05], + ['O16',0.037237881492], + ['O17',1.4118507999999999e-05], + ['N14',0.0021624], + ['H1',0.058196]]) +# Material Name: Aluminum Tank +m2 = mcdc.material(nuclides=[ + ['Al27',0.059469]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.505, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=16.825, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.64, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=22.53, bc='interface') +s6 = mcdc.surface('plane-z', z=49.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..70c8a14 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/generate_materials.py @@ -0,0 +1,32 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8310e-06) +mat.add_nuclide('U235', 3.4777e-04) +mat.add_nuclide('U236', 1.6130e-06) +mat.add_nuclide('U238', 1.9798e-05) +mat.add_element('O', 3.5037e-02) +mat.add_nuclide('N14', 9.2307e-04) +mat.add_nuclide('H1', 6.3220e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('C', 2.6231e-04) +mat.add_element('Si', 1.3768e-03) +mat.add_element('P', 3.8530e-05) +mat.add_element('S', 2.8282e-05) +mat.add_element('Cr', 1.6985e-02) +mat.add_element('Mn', 1.1209e-03) +mat.add_element('Fe', 5.9852e-02) +mat.add_element('Ni', 7.5400e-03) +mat.add_element('Mo', 8.9563e-06) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/geometry.xml new file mode 100644 index 0000000..49fc30f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/materials.xml new file mode 100644 index 0000000..e40deb5 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-10/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..e305246 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.6817e-06) +mat.add_nuclide('U235', 1.5266e-04) +mat.add_nuclide('U236', 7.0808e-07) +mat.add_nuclide('U238', 8.6908e-06) +mat.add_element('O', 3.4101e-02) +mat.add_nuclide('N14', 3.9433e-04) +mat.add_nuclide('H1', 6.5247e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-10/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/geometry.xml new file mode 100644 index 0000000..f5335b7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-10/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/materials.xml new file mode 100644 index 0000000..47142d1 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-10/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-10/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..eb3f907 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/generate_materials.py @@ -0,0 +1,32 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 9.1180e-06) +mat.add_nuclide('U235', 8.2771e-04) +mat.add_nuclide('U236', 3.8392e-06) +mat.add_nuclide('U238', 4.7120e-05) +mat.add_element('O', 3.7135e-02) +mat.add_nuclide('N14', 2.1020e-03) +mat.add_nuclide('H1', 5.8433e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('C', 2.6231e-04) +mat.add_element('Si', 1.3768e-03) +mat.add_element('P', 3.8530e-05) +mat.add_element('S', 2.8282e-05) +mat.add_element('Cr', 1.6985e-02) +mat.add_element('Mn', 1.1209e-03) +mat.add_element('Fe', 5.9852e-02) +mat.add_element('Ni', 7.5400e-03) +mat.add_element('Mo', 8.9563e-06) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/geometry.xml new file mode 100644 index 0000000..611a518 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/materials.xml new file mode 100644 index 0000000..d6428ab --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..72aa914 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.7584e-06) +mat.add_nuclide('U235', 3.4118e-04) +mat.add_nuclide('U236', 1.5825e-06) +mat.add_nuclide('U238', 1.9423e-05) +mat.add_element('O', 3.5033e-02) +mat.add_nuclide('N14', 9.0231e-04) +mat.add_nuclide('H1', 6.3359e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/geometry.xml new file mode 100644 index 0000000..3b2aa59 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/materials.xml new file mode 100644 index 0000000..ef2139f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..11558b0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 9.4068e-06) +mat.add_nuclide('U235', 8.5392e-04) +mat.add_nuclide('U236', 3.9607e-06) +mat.add_nuclide('U238', 4.8613e-05) +mat.add_element('O', 3.7252e-02) +mat.add_nuclide('N14', 2.1624e-03) +mat.add_nuclide('H1', 5.8196e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/geometry.xml new file mode 100644 index 0000000..7543246 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/materials.xml new file mode 100644 index 0000000..0daf8fb --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..5db3f0e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.4435e-06) +mat.add_nuclide('U235', 1.3103e-04) +mat.add_nuclide('U236', 6.0777e-07) +mat.add_nuclide('U238', 7.4595e-06) +mat.add_element('O', 3.4003e-02) +mat.add_nuclide('N14', 3.4432e-04) +mat.add_nuclide('H1', 6.5441e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-5/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/geometry.xml new file mode 100644 index 0000000..369a59e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-5/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/materials.xml new file mode 100644 index 0000000..8ba2284 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-5/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..c6f5124 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5686e-06) +mat.add_nuclide('U235', 1.4240e-04) +mat.add_nuclide('U236', 6.6047e-07) +mat.add_nuclide('U238', 8.1064e-06) +mat.add_element('O', 3.4057e-02) +mat.add_nuclide('N14', 3.7412e-04) +mat.add_nuclide('H1', 6.5327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-6/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/geometry.xml new file mode 100644 index 0000000..95897c9 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-6/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/materials.xml new file mode 100644 index 0000000..ada73e3 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-6/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-7/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..7fd2b9c --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.6132e-06) +mat.add_nuclide('U235', 3.2800e-04) +mat.add_nuclide('U236', 1.5214e-06) +mat.add_nuclide('U238', 1.8673e-05) +mat.add_element('O', 3.4945e-02) +mat.add_nuclide('N14', 8.7645e-04) +mat.add_nuclide('H1', 6.3397e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-7/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/geometry.xml new file mode 100644 index 0000000..de76660 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-7/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/materials.xml new file mode 100644 index 0000000..4464f40 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-7/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-7/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-8/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..6aa3ecf --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8310e-06) +mat.add_nuclide('U235', 3.4777e-04) +mat.add_nuclide('U236', 1.6130e-06) +mat.add_nuclide('U238', 1.9798e-05) +mat.add_element('O', 3.5037e-02) +mat.add_nuclide('N14', 9.2307e-04) +mat.add_nuclide('H1', 6.3220e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-8/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/geometry.xml new file mode 100644 index 0000000..1e3fcf0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-8/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/materials.xml new file mode 100644 index 0000000..745fad7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-8/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-8/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-9/generate_materials.py b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..11558b0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 9.4068e-06) +mat.add_nuclide('U235', 8.5392e-04) +mat.add_nuclide('U236', 3.9607e-06) +mat.add_nuclide('U238', 4.8613e-05) +mat.add_element('O', 3.7252e-02) +mat.add_nuclide('N14', 2.1624e-03) +mat.add_nuclide('H1', 5.8196e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum Tank" +mat.set_density('sum') +mat.add_nuclide('Al27', 5.9469e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-9/geometry.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/geometry.xml new file mode 100644 index 0000000..bb3bc8b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-9/materials.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/materials.xml new file mode 100644 index 0000000..0daf8fb --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-001/openmc/case-9/settings.xml b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-001/openmc/case-9/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-1.py b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-1.py new file mode 100644 index 0000000..1d6cd5f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-1.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0017396999999999998], + ['U238',9.7761e-05], + ['F19',0.0037129], + ['O16',0.033448318281], + ['O17',1.2681718999999998e-05], + ['H2',0.059318], + ['H1',0.00017849]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Heavy Water +# S(a,b): c_D_in_D2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H2',0.066078], + ['H1',0.00039886], + ['O16',0.033225402797999994], + ['O17',1.2597201999999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.088, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.189, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.367, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.621, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-2.py b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-2.py new file mode 100644 index 0000000..b602cb6 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-2.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.001135], + ['U238',6.3782e-05], + ['F19',0.0024224], + ['O16',0.032885531658], + ['O17',1.2468341999999999e-05], + ['H2',0.060768], + ['H1',0.00018285]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Heavy Water +# S(a,b): c_D_in_D2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H2',0.066078], + ['H1',0.00039886], + ['O16',0.033225402797999994], + ['O17',1.2597201999999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=18.401, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=18.503, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.411, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.665, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-3.py b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-3.py new file mode 100644 index 0000000..438b4bc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-3.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00077376], + ['U238',4.3482e-05], + ['F19',0.0016514], + ['O16',0.033053467986], + ['O17',1.2532014e-05], + ['H2',0.062641], + ['H1',0.00018849]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Heavy Water +# S(a,b): c_D_in_D2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H2',0.066078], + ['H1',0.00039886], + ['O16',0.033225402797999994], + ['O17',1.2597201999999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.633, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.735, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.373, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.627, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-4.py b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-4.py new file mode 100644 index 0000000..24ce70e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-4.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00047399000000000003], + ['U238',2.6635999999999997e-05], + ['F19',0.0010116], + ['O16',0.033064463817000005], + ['O17',1.2536183e-05], + ['H2',0.063939], + ['H1',0.00019239]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Heavy Water +# S(a,b): c_D_in_D2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H2',0.066078], + ['H1',0.00039886], + ['O16',0.033225402797999994], + ['O17',1.2597201999999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.874, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.976, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.344, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.598, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-5.py b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-5.py new file mode 100644 index 0000000..9696ae5 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-5.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00026646], + ['U238',1.4974e-05], + ['F19',0.0005687], + ['O16',0.032931514224], + ['O17',1.2485776000000003e-05], + ['H2',0.064556], + ['H1',0.00019424999999999998]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Heavy Water +# S(a,b): c_D_in_D2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H2',0.066078], + ['H1',0.00039886], + ['O16',0.033225402797999994], + ['O17',1.2597201999999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.211, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.313, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.411, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.665, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-6.py b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-6.py new file mode 100644 index 0000000..183d78b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/mcdc/heu-sol-therm-004_case-6.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00015373], + ['U238',8.6387e-06], + ['F19',0.00032809], + ['O16',0.033443320176], + ['O17',1.2679823999999999e-05], + ['H2',0.066058], + ['H1',0.00019877000000000002]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Heavy Water +# S(a,b): c_D_in_D2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H2',0.066078], + ['H1',0.00039886], + ['O16',0.033225402797999994], + ['O17',1.2597201999999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=23.419, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=23.52, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.348, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.602, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..ba6ad6e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.9029e-05) +mat.add_nuclide('U235', 1.7397e-03) +mat.add_nuclide('U238', 9.7761e-05) +mat.add_nuclide('F19', 3.7129e-03) +mat.add_element('O', 3.3461e-02) +mat.add_nuclide('H2', 5.9318e-02) +mat.add_nuclide('H1', 1.7849e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Heavy Water" +mat.set_density('sum') +mat.add_nuclide('H2', 6.6078e-02) +mat.add_nuclide('H1', 3.9886e-04) +mat.add_element('O', 3.3238e-02) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/geometry.xml new file mode 100644 index 0000000..61a73c2 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/materials.xml new file mode 100644 index 0000000..374003e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..4c72bd7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2415e-05) +mat.add_nuclide('U235', 1.1350e-03) +mat.add_nuclide('U238', 6.3782e-05) +mat.add_nuclide('F19', 2.4224e-03) +mat.add_element('O', 3.2898e-02) +mat.add_nuclide('H2', 6.0768e-02) +mat.add_nuclide('H1', 1.8285e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Heavy Water" +mat.set_density('sum') +mat.add_nuclide('H2', 6.6078e-02) +mat.add_nuclide('H1', 3.9886e-04) +mat.add_element('O', 3.3238e-02) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/geometry.xml new file mode 100644 index 0000000..3249234 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/materials.xml new file mode 100644 index 0000000..212ef8f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..52e885e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 8.4636e-06) +mat.add_nuclide('U235', 7.7376e-04) +mat.add_nuclide('U238', 4.3482e-05) +mat.add_nuclide('F19', 1.6514e-03) +mat.add_element('O', 3.3066e-02) +mat.add_nuclide('H2', 6.2641e-02) +mat.add_nuclide('H1', 1.8849e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Heavy Water" +mat.set_density('sum') +mat.add_nuclide('H2', 6.6078e-02) +mat.add_nuclide('H1', 3.9886e-04) +mat.add_element('O', 3.3238e-02) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/geometry.xml new file mode 100644 index 0000000..56eb428 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/materials.xml new file mode 100644 index 0000000..2be2b4e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..d8fab52 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.1847e-06) +mat.add_nuclide('U235', 4.7399e-04) +mat.add_nuclide('U238', 2.6636e-05) +mat.add_nuclide('F19', 1.0116e-03) +mat.add_element('O', 3.3077e-02) +mat.add_nuclide('H2', 6.3939e-02) +mat.add_nuclide('H1', 1.9239e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Heavy Water" +mat.set_density('sum') +mat.add_nuclide('H2', 6.6078e-02) +mat.add_nuclide('H1', 3.9886e-04) +mat.add_element('O', 3.3238e-02) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/geometry.xml new file mode 100644 index 0000000..af8f6b7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/materials.xml new file mode 100644 index 0000000..44ba7f4 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..1494f72 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 2.9146e-06) +mat.add_nuclide('U235', 2.6646e-04) +mat.add_nuclide('U238', 1.4974e-05) +mat.add_nuclide('F19', 5.6870e-04) +mat.add_element('O', 3.2944e-02) +mat.add_nuclide('H2', 6.4556e-02) +mat.add_nuclide('H1', 1.9425e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Heavy Water" +mat.set_density('sum') +mat.add_nuclide('H2', 6.6078e-02) +mat.add_nuclide('H1', 3.9886e-04) +mat.add_element('O', 3.3238e-02) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-5/geometry.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/geometry.xml new file mode 100644 index 0000000..749568b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-5/materials.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/materials.xml new file mode 100644 index 0000000..d909849 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-5/settings.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..7a9753d --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.6815e-06) +mat.add_nuclide('U235', 1.5373e-04) +mat.add_nuclide('U238', 8.6387e-06) +mat.add_nuclide('F19', 3.2809e-04) +mat.add_element('O', 3.3456e-02) +mat.add_nuclide('H2', 6.6058e-02) +mat.add_nuclide('H1', 1.9877e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Heavy Water" +mat.set_density('sum') +mat.add_nuclide('H2', 6.6078e-02) +mat.add_nuclide('H1', 3.9886e-04) +mat.add_element('O', 3.3238e-02) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-6/geometry.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/geometry.xml new file mode 100644 index 0000000..41f54e5 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-6/materials.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/materials.xml new file mode 100644 index 0000000..fec0311 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-004/openmc/case-6/settings.xml b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-004/openmc/case-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-1.py b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-1.py new file mode 100644 index 0000000..14dffb3 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-1.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0016626], + ['U238',9.4079e-05], + ['F19',0.0035663000000000005], + ['O16',0.03334735656], + ['O17',1.264344e-05], + ['H1',0.05958700000000001]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.5177, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.6764, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-2.py b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-2.py new file mode 100644 index 0000000..a663516 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-2.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0012965], + ['U238',7.3359e-05], + ['F19',0.0027809], + ['O16',0.033383342916], + ['O17',1.2657084e-05], + ['H1',0.061229000000000006]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.4695, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.5282, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-3.py b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-3.py new file mode 100644 index 0000000..4100de8 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-3.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0008328099999999999], + ['U238',4.7124e-05], + ['F19',0.0017864], + ['O16',0.033454316006999996], + ['O17',1.2683992999999998e-05], + ['H1',0.063362]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.5177, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.6764, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-4.py b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-4.py new file mode 100644 index 0000000..bf8ffa6 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/mcdc/heu-sol-therm-009_case-4.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00050898], + ['U238',2.88e-05], + ['F19',0.0010917], + ['O16',0.033265387638], + ['O17',1.2612362e-05], + ['H1',0.064373]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.8442, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.0029, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..5492ad3 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.7561e-05) +mat.add_nuclide('U235', 1.6626e-03) +mat.add_nuclide('U236', 8.8837e-06) +mat.add_nuclide('U238', 9.4079e-05) +mat.add_nuclide('F19', 3.5663e-03) +mat.add_element('O', 3.3360e-02) +mat.add_nuclide('H1', 5.9587e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/geometry.xml new file mode 100644 index 0000000..2efa55a --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/materials.xml new file mode 100644 index 0000000..3633f23 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..2ea45a4 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.3694e-05) +mat.add_nuclide('U235', 1.2965e-03) +mat.add_nuclide('U236', 6.9272e-06) +mat.add_nuclide('U238', 7.3359e-05) +mat.add_nuclide('F19', 2.7809e-03) +mat.add_element('O', 3.3396e-02) +mat.add_nuclide('H1', 6.1229e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/geometry.xml new file mode 100644 index 0000000..1c10934 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/materials.xml new file mode 100644 index 0000000..16ab336 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..3653192 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 8.7965e-06) +mat.add_nuclide('U235', 8.3281e-04) +mat.add_nuclide('U236', 4.4499e-06) +mat.add_nuclide('U238', 4.7124e-05) +mat.add_nuclide('F19', 1.7864e-03) +mat.add_element('O', 3.3467e-02) +mat.add_nuclide('H1', 6.3362e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/geometry.xml new file mode 100644 index 0000000..d7aaee5 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/materials.xml new file mode 100644 index 0000000..b4c3209 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..2345c00 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.3760e-06) +mat.add_nuclide('U235', 5.0898e-04) +mat.add_nuclide('U236', 2.7195e-06) +mat.add_nuclide('U238', 2.8800e-05) +mat.add_nuclide('F19', 1.0917e-03) +mat.add_element('O', 3.3278e-02) +mat.add_nuclide('H1', 6.4373e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/geometry.xml new file mode 100644 index 0000000..9715d31 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/materials.xml new file mode 100644 index 0000000..aadecad --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-009/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-009/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-1.py b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-1.py new file mode 100644 index 0000000..ab35d2c --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-1.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00024354], + ['U238',1.3607e-05], + ['F19',0.00052267], + ['O16',0.033384342537000004], + ['O17',1.2657462999999999e-05], + ['H1',0.065749]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 27.5 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066614], + ['O16',0.033294376647], + ['O17',1.2623353000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.2123, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.3393, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-2.py b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-2.py new file mode 100644 index 0000000..5742c53 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-2.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00024768], + ['U238',1.3839e-05], + ['F19',0.00053157], + ['O16',0.033242396355], + ['O17',1.2603645e-05], + ['H1',0.065447]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 39.5 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066348], + ['O16',0.033161427054], + ['O17',1.2572946000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.2187, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.3457, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-3.py b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-3.py new file mode 100644 index 0000000..3330c8d --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-3.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00026109], + ['U238',1.4588e-05], + ['F19',0.00056035], + ['O16',0.032623630955999995], + ['O17',1.2369044e-05], + ['H1',0.064151]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 74.0 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.065214], + ['O16',0.032594641947], + ['O17',1.2358053e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.2359, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.3629, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-4.py b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-4.py new file mode 100644 index 0000000..16c9b84 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/mcdc/heu-sol-therm-010_case-4.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00026609], + ['U238',1.4867e-05], + ['F19',0.00057107], + ['O16',0.032358731391], + ['O17',1.2268609000000001e-05], + ['H1',0.0636]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector at 85.5 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.064736], + ['O16',0.032355732528], + ['O17',1.2267472e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.2418, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.3688, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..9f3d3b1 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 2.8888e-06) +mat.add_nuclide('U235', 2.4354e-04) +mat.add_nuclide('U236', 1.3020e-06) +mat.add_nuclide('U238', 1.3607e-05) +mat.add_nuclide('F19', 5.2267e-04) +mat.add_element('O', 3.3397e-02) +mat.add_nuclide('H1', 6.5749e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 27.5 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6614e-02) +mat.add_element('O', 3.3307e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/geometry.xml new file mode 100644 index 0000000..12263d7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/materials.xml new file mode 100644 index 0000000..5e3b3f8 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..0e4d9be --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 2.9381e-06) +mat.add_nuclide('U235', 2.4768e-04) +mat.add_nuclide('U236', 1.3241e-06) +mat.add_nuclide('U238', 1.3839e-05) +mat.add_nuclide('F19', 5.3157e-04) +mat.add_element('O', 3.3255e-02) +mat.add_nuclide('H1', 6.5447e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 39.5 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6348e-02) +mat.add_element('O', 3.3174e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/geometry.xml new file mode 100644 index 0000000..ba7aacf --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/materials.xml new file mode 100644 index 0000000..ec1101a --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..c52172c --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.0971e-06) +mat.add_nuclide('U235', 2.6109e-04) +mat.add_nuclide('U236', 1.3958e-06) +mat.add_nuclide('U238', 1.4588e-05) +mat.add_nuclide('F19', 5.6035e-04) +mat.add_element('O', 3.2636e-02) +mat.add_nuclide('H1', 6.4151e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 74.0 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.5214e-02) +mat.add_element('O', 3.2607e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/geometry.xml new file mode 100644 index 0000000..f636d70 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/materials.xml new file mode 100644 index 0000000..84b4ec7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..39d630e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.1564e-06) +mat.add_nuclide('U235', 2.6609e-04) +mat.add_nuclide('U236', 1.4225e-06) +mat.add_nuclide('U238', 1.4867e-05) +mat.add_nuclide('F19', 5.7107e-04) +mat.add_element('O', 3.2371e-02) +mat.add_nuclide('H1', 6.3600e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector at 85.5 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.4736e-02) +mat.add_element('O', 3.2368e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/geometry.xml new file mode 100644 index 0000000..3969bac --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/materials.xml new file mode 100644 index 0000000..115a5b2 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-010/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-010/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-011/mcdc/heu-sol-therm-011_case-1.py b/icsbep/openmc/heu-sol-therm-011/mcdc/heu-sol-therm-011_case-1.py new file mode 100644 index 0000000..4604d4c --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/mcdc/heu-sol-therm-011_case-1.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00012657], + ['U238',7.162e-06], + ['F19',0.00027149], + ['O16',0.033383342916], + ['O17',1.2657084000000002e-05], + ['H1',0.066248]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.9572, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.0842, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-011/mcdc/heu-sol-therm-011_case-2.py b/icsbep/openmc/heu-sol-therm-011/mcdc/heu-sol-therm-011_case-2.py new file mode 100644 index 0000000..506d009 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/mcdc/heu-sol-therm-011_case-2.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0001244], + ['U238',7.039299999999999e-06], + ['F19',0.00026684], + ['O16',0.033414331166999996], + ['O17',1.2668833000000002e-05], + ['H1',0.06632]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.9569, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.0839, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=35.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..1f3cbe9 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.3369e-06) +mat.add_nuclide('U235', 1.2657e-04) +mat.add_nuclide('U236', 6.7629e-07) +mat.add_nuclide('U238', 7.1620e-06) +mat.add_nuclide('F19', 2.7149e-04) +mat.add_element('O', 3.3396e-02) +mat.add_nuclide('H1', 6.6248e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/geometry.xml new file mode 100644 index 0000000..8820c5e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/materials.xml new file mode 100644 index 0000000..babdb22 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..2b0538c --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.3140e-06) +mat.add_nuclide('U235', 1.2440e-04) +mat.add_nuclide('U236', 6.6471e-07) +mat.add_nuclide('U238', 7.0393e-06) +mat.add_nuclide('F19', 2.6684e-04) +mat.add_element('O', 3.3427e-02) +mat.add_nuclide('H1', 6.6320e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/geometry.xml new file mode 100644 index 0000000..fcb8edf --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/materials.xml new file mode 100644 index 0000000..efaa979 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-011/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-011/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-012/mcdc/heu-sol-therm-012.py b/icsbep/openmc/heu-sol-therm-012/mcdc/heu-sol-therm-012.py new file mode 100644 index 0000000..5d93e40 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-012/mcdc/heu-sol-therm-012.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.244400000000001e-05], + ['U238',2.9675e-06], + ['F19',0.00011249], + ['O16',0.033460313733], + ['O17',1.2686267e-05], + ['H1',0.066722]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water Reflector +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=27.9244, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=28.1244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.1244, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-012/openmc/generate_materials.py b/icsbep/openmc/heu-sol-therm-012/openmc/generate_materials.py new file mode 100644 index 0000000..48b39e8 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-012/openmc/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.5393e-07) +mat.add_nuclide('U235', 5.2444e-05) +mat.add_nuclide('U236', 2.8022e-07) +mat.add_nuclide('U238', 2.9675e-06) +mat.add_nuclide('F19', 1.1249e-04) +mat.add_element('O', 3.3473e-02) +mat.add_nuclide('H1', 6.6722e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water Reflector" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-012/openmc/geometry.xml b/icsbep/openmc/heu-sol-therm-012/openmc/geometry.xml new file mode 100644 index 0000000..f46c60b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-012/openmc/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-012/openmc/materials.xml b/icsbep/openmc/heu-sol-therm-012/openmc/materials.xml new file mode 100644 index 0000000..ad6983e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-012/openmc/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-012/openmc/settings.xml b/icsbep/openmc/heu-sol-therm-012/openmc/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-012/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-1.py b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-1.py new file mode 100644 index 0000000..91428fb --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-1.py @@ -0,0 +1,64 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.8042e-05], + ['U238',2.805e-06], + ['N14',0.00018616556845], + ['N15',6.8443155e-07], + ['O16',0.033629249682], + ['O17',1.2750318e-05], + ['H1',0.066041]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.5948, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.9148, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-2.py b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-2.py new file mode 100644 index 0000000..65e4929 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-2.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.6171e-05], + ['U238',3.2796e-06], + ['N14',0.00021198066011999996], + ['N15',7.793398799999999e-07], + ['B10',1.0366e-06], + ['B11',4.1724e-06], + ['O16',0.033654240207], + ['O17',1.2759792999999999e-05], + ['H1',0.065892]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.5948, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.9148, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-3.py b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-3.py new file mode 100644 index 0000000..5a3418d --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-3.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.3904e-05], + ['U238',3.7311000000000006e-06], + ['N14',0.00023821421333], + ['N15',8.7578667e-07], + ['B10',2.0725e-06], + ['B11',8.3421e-06], + ['O16',0.033713217845999996], + ['O17',1.2782154e-05], + ['H1',0.065815]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.5948, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.9148, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-4.py b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-4.py new file mode 100644 index 0000000..9176e14 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/mcdc/heu-sol-therm-013_case-4.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.7926e-05], + ['U238',3.9659e-06], + ['N14',0.00025369729031], + ['N15',9.3270969e-07], + ['B10',2.5472e-06], + ['B11',1.0253e-05], + ['O16',0.033831173124], + ['O17',1.2826876e-05], + ['H1',0.065964]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.5948, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.9148, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..11d08a4 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +un = openmc.Material(name="Uranium Nitrate Solution") +un.add_nuclide('U234', 5.3850e-07) +un.add_nuclide('U235', 4.8042e-05) +un.add_nuclide('U236', 1.3862e-07) +un.add_nuclide('U238', 2.8050e-06) +un.add_element('N', 1.8685e-04) +un.add_element('O', 3.3642e-02) +un.add_nuclide('H1', 6.6041e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +aluminum = openmc.Material(name="Type 1100 Aluminum") +aluminum.add_element('Al', 5.9699e-02) +aluminum.add_element('Si', 5.5202e-04) +aluminum.add_element('Cu', 5.1364e-05) +aluminum.add_element('Zn', 2.4958e-05) +aluminum.add_element('Mn', 1.4853e-05) + +materials = openmc.Materials([un, aluminum]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/geometry.xml new file mode 100644 index 0000000..9981d3e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/materials.xml new file mode 100644 index 0000000..87a62c9 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/materials.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..8219555 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +un = openmc.Material(name = "Uranium Nitrate Solution") +un.add_nuclide('U234', 6.2962e-07) +un.add_nuclide('U235', 5.6171e-05) +un.add_nuclide('U236', 1.6207e-07) +un.add_nuclide('U238', 3.2796e-06) +un.add_element('N', 2.1276e-04) +un.add_nuclide('B10', 1.0366e-06) +un.add_nuclide('B11', 4.1724e-06) +un.add_element('O', 3.3667e-02) +un.add_nuclide('H1', 6.5892e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +aluminum = openmc.Material(name="Type 1100 Aluminum") +aluminum.add_element('Al', 5.9699e-02) +aluminum.add_element('Si', 5.5202e-04) +aluminum.add_element('Cu', 5.1364e-05) +aluminum.add_element('Zn', 2.4958e-05) +aluminum.add_element('Mn', 1.4853e-05) + +materials = openmc.Materials([un, aluminum]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/geometry.xml new file mode 100644 index 0000000..f3d7a9a --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/materials.xml new file mode 100644 index 0000000..0afba31 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/materials.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..35a2218 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +un = openmc.Material(name="Uranium Nitrate Solution") +un.add_nuclide('U234', 7.1630e-07) +un.add_nuclide('U235', 6.3904e-05) +un.add_nuclide('U236', 1.8438e-07) +un.add_nuclide('U238', 3.7311e-06) +un.add_element('N', 2.3909e-04) +un.add_nuclide('B10', 2.0725e-06) +un.add_nuclide('B11', 8.3421e-06) +un.add_element('O', 3.3726e-02) +un.add_nuclide('H1', 6.5815e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +aluminum = openmc.Material(name="Type 1100 Aluminum") +aluminum.add_element('Al', 5.9699e-02) +aluminum.add_element('Si', 5.5202e-04) +aluminum.add_element('Cu', 5.1364e-05) +aluminum.add_element('Zn', 2.4958e-05) +aluminum.add_element('Mn', 1.4853e-05) + +materials = openmc.Materials([un, aluminum]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/geometry.xml new file mode 100644 index 0000000..e7eb6cb --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/materials.xml new file mode 100644 index 0000000..2a0c9c2 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/materials.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..31e07cd --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +un = openmc.Material(name="Uranium Nitrate Solution") +un.add_nuclide('U234', 7.6139e-07) +un.add_nuclide('U235', 6.7926e-05) +un.add_nuclide('U236', 1.9599e-07) +un.add_nuclide('U238', 3.9659e-06) +un.add_element('N', 2.5463e-04) +un.add_nuclide('B10', 2.5472e-06) +un.add_nuclide('B11', 1.0253e-05) +un.add_element('O', 3.3844e-02) +un.add_nuclide('H1', 6.5964e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +aluminum = openmc.Material(name="Type 1100 Aluminum") +aluminum.add_element('Al', 5.9699e-02) +aluminum.add_element('Si', 5.5202e-04) +aluminum.add_element('Cu', 5.1364e-05) +aluminum.add_element('Zn', 2.4958e-05) +aluminum.add_element('Mn', 1.4853e-05) + +materials = openmc.Materials([un, aluminum]) +materials.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/geometry.xml new file mode 100644 index 0000000..2a4875a --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/materials.xml new file mode 100644 index 0000000..4c51716 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/materials.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-013/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-013/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-1.py b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-1.py new file mode 100644 index 0000000..5e1971b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-1.py @@ -0,0 +1,92 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.0002802], + ['U238',1.5751e-05], + ['F19',0.00059823], + ['O16',0.032819556672], + ['O17',1.2443327999999998e-05], + ['H2',0.063823], + ['H1',0.00064468]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Dry Air +m3 = mcdc.material(nuclides=[ + ['N14',3.2150798653e-05], + ['N15',1.1820134700000002e-07], + ['O16',8.6536190349e-06], + ['O17',3.2809650999999998e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-0.3175, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=71.45, bc='interface') +s4 = mcdc.surface('plane-z', z=121.92, bc='interface') +s5 = mcdc.surface('plane-z', z=122.8725, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1113, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.27, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=31.6, bc='interface') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=31.9175, bc='vacuum') +s10 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.27, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.5875, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s9, fill=m2) +c2 = mcdc.cell(+s2 & -s4 & +s8 & -s9, fill=m2) +c3 = mcdc.cell(+s4 & -s5 & +s7 & -s9 & +s11, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s11, fill=m1) +c5 = mcdc.cell(+s3 & -s4 & +s7 & -s8 & +s11, fill=m3) +c6 = mcdc.cell(+s2 & -s5 & -s6, fill=m3) +c7 = mcdc.cell(+s2 & -s5 & +s6 & -s7, fill=m2) +c8 = mcdc.cell(+s2 & -s3 & -s10, fill=m1) +c9 = mcdc.cell(+s3 & -s5 & -s10, fill=m3) +c10 = mcdc.cell(+s2 & -s5 & +s10 & -s11, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,30.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-2.py b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-2.py new file mode 100644 index 0000000..19abec3 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-2.py @@ -0,0 +1,92 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00015629], + ['U238',8.7827e-06], + ['F19',0.00033356], + ['O16',0.033063464196], + ['O17',1.2535803999999999e-05], + ['H2',0.06483], + ['H1',0.00065485]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Dry Air +m3 = mcdc.material(nuclides=[ + ['N14',3.2150798653e-05], + ['N15',1.1820134700000002e-07], + ['O16',8.6536190349e-06], + ['O17',3.2809650999999998e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-0.3175, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=78.74, bc='interface') +s4 = mcdc.surface('plane-z', z=121.92, bc='interface') +s5 = mcdc.surface('plane-z', z=122.8725, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1113, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.27, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=31.6, bc='interface') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=31.9175, bc='vacuum') +s10 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.27, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.5875, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s9, fill=m2) +c2 = mcdc.cell(+s2 & -s4 & +s8 & -s9, fill=m2) +c3 = mcdc.cell(+s4 & -s5 & +s7 & -s9 & +s11, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s11, fill=m1) +c5 = mcdc.cell(+s3 & -s4 & +s7 & -s8 & +s11, fill=m3) +c6 = mcdc.cell(+s2 & -s5 & -s6, fill=m3) +c7 = mcdc.cell(+s2 & -s5 & +s6 & -s7, fill=m2) +c8 = mcdc.cell(+s2 & -s3 & -s10, fill=m1) +c9 = mcdc.cell(+s3 & -s5 & -s10, fill=m3) +c10 = mcdc.cell(+s2 & -s5 & +s10 & -s11, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,30.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-3.py b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-3.py new file mode 100644 index 0000000..7d62fc5 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-3.py @@ -0,0 +1,92 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.712e-05], + ['U238',4.3338e-06], + ['F19',0.00016459], + ['O16',0.033159427812], + ['O17',1.2572188000000002e-05], + ['H2',0.065354], + ['H1',0.00066014]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Dry Air +m3 = mcdc.material(nuclides=[ + ['N14',3.2150798653e-05], + ['N15',1.1820134700000002e-07], + ['O16',8.6536190349e-06], + ['O17',3.2809650999999998e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-0.3175, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=61.09, bc='interface') +s4 = mcdc.surface('plane-z', z=121.92, bc='interface') +s5 = mcdc.surface('plane-z', z=122.8725, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1113, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.27, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=38.1, bc='interface') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=38.4175, bc='vacuum') +s10 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.27, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.5875, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s9, fill=m2) +c2 = mcdc.cell(+s2 & -s4 & +s8 & -s9, fill=m2) +c3 = mcdc.cell(+s4 & -s5 & +s7 & -s9 & +s11, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s11, fill=m1) +c5 = mcdc.cell(+s3 & -s4 & +s7 & -s8 & +s11, fill=m3) +c6 = mcdc.cell(+s2 & -s5 & -s6, fill=m3) +c7 = mcdc.cell(+s2 & -s5 & +s6 & -s7, fill=m2) +c8 = mcdc.cell(+s2 & -s3 & -s10, fill=m1) +c9 = mcdc.cell(+s3 & -s5 & -s10, fill=m3) +c10 = mcdc.cell(+s2 & -s5 & +s10 & -s11, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,30.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-4.py b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-4.py new file mode 100644 index 0000000..c7b9ade --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-4.py @@ -0,0 +1,95 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.712e-05], + ['U238',4.3338e-06], + ['F19',0.00016459], + ['O16',0.033159427812], + ['O17',1.2572188000000002e-05], + ['H2',0.065354], + ['H1',0.00066014]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Dry Air +m3 = mcdc.material(nuclides=[ + ['N14',3.2150798653e-05], + ['N15',1.1820134700000002e-07], + ['O16',8.6536190349e-06], + ['O17',3.2809650999999998e-09]]) +# Material Name: Aluminum +m4 = mcdc.material(nuclides=[ + ['Al27',0.060262]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-0.3175, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=60.83, bc='interface') +s4 = mcdc.surface('plane-z', z=121.92, bc='interface') +s5 = mcdc.surface('plane-z', z=122.8725, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.27, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.42875, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=38.1, bc='interface') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=38.4175, bc='vacuum') +s10 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.27, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.5875, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s9, fill=m2) +c2 = mcdc.cell(+s2 & -s4 & +s8 & -s9, fill=m2) +c3 = mcdc.cell(+s4 & -s5 & +s7 & -s9 & +s11, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s11, fill=m1) +c5 = mcdc.cell(+s3 & -s4 & +s7 & -s8 & +s11, fill=m3) +c6 = mcdc.cell(+s2 & -s5 & -s6, fill=m3) +c7 = mcdc.cell(+s2 & -s5 & +s6 & -s7, fill=m4) +c8 = mcdc.cell(+s2 & -s3 & -s10, fill=m1) +c9 = mcdc.cell(+s3 & -s5 & -s10, fill=m3) +c10 = mcdc.cell(+s2 & -s5 & +s10 & -s11, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,30.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-5.py b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-5.py new file mode 100644 index 0000000..8181523 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/mcdc/heu-sol-therm-020_case-5.py @@ -0,0 +1,95 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2F2/D2O Solution +# S(a,b): c_D_in_D2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.177e-05], + ['U238',1.7852999999999999e-06], + ['F19',6.7806e-05], + ['O16',0.033112445625], + ['O17',1.2554375e-05], + ['H2',0.065453], + ['H1',0.00066114]]) +# Material Name: 321 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.054460586699999994], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.00071740295], + ['Cr52',0.01383440179], + ['Cr53',0.0015687101100000003], + ['Cr54',0.00039048515000000004], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.80036997e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363], + ['Si28',0.00156624442576], + ['Si29',7.952942312e-05], + ['Si30',5.242615112e-05]]) +# Material Name: Dry Air +m3 = mcdc.material(nuclides=[ + ['N14',3.2150798653e-05], + ['N15',1.1820134700000002e-07], + ['O16',8.6536190349e-06], + ['O17',3.2809650999999998e-09]]) +# Material Name: Aluminum +m4 = mcdc.material(nuclides=[ + ['Al27',0.060262]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-0.3175, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s3 = mcdc.surface('plane-z', z=84.75, bc='interface') +s4 = mcdc.surface('plane-z', z=121.92, bc='interface') +s5 = mcdc.surface('plane-z', z=122.8725, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.27, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.42875, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=38.1, bc='interface') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=38.4175, bc='vacuum') +s10 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.27, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[21.59, 0.0], radius=1.5875, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s9, fill=m2) +c2 = mcdc.cell(+s2 & -s4 & +s8 & -s9, fill=m2) +c3 = mcdc.cell(+s4 & -s5 & +s7 & -s9 & +s11, fill=m2) +c4 = mcdc.cell(+s2 & -s3 & +s7 & -s8 & +s11, fill=m1) +c5 = mcdc.cell(+s3 & -s4 & +s7 & -s8 & +s11, fill=m3) +c6 = mcdc.cell(+s2 & -s5 & -s6, fill=m3) +c7 = mcdc.cell(+s2 & -s5 & +s6 & -s7, fill=m4) +c8 = mcdc.cell(+s2 & -s3 & -s10, fill=m1) +c9 = mcdc.cell(+s3 & -s5 & -s10, fill=m3) +c10 = mcdc.cell(+s2 & -s5 & +s10 & -s11, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,30.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..790e762 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.0660e-06) +mat.add_nuclide('U235', 2.8020e-04) +mat.add_nuclide('U238', 1.5751e-05) +mat.add_element('F', 5.9823e-04) +mat.add_element('O', 3.2832e-02) +mat.add_nuclide('H2', 6.3823e-02) +mat.add_nuclide('H1', 6.4468e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Dry Air" +mat.set_density('sum') +mat.add_element('N', 3.2269e-05) +mat.add_element('O', 8.6569e-06) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/geometry.xml new file mode 100644 index 0000000..5ec6d1b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/geometry.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/materials.xml new file mode 100644 index 0000000..c3b2805 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/materials.xml @@ -0,0 +1,42 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/settings.xml new file mode 100644 index 0000000..5fff893 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 30. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..14a2b46 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 1.7095e-06) +mat.add_nuclide('U235', 1.5629e-04) +mat.add_nuclide('U238', 8.7827e-06) +mat.add_element('F', 3.3356e-04) +mat.add_element('O', 3.3076e-02) +mat.add_nuclide('H2', 6.4830e-02) +mat.add_nuclide('H1', 6.5485e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Dry Air" +mat.set_density('sum') +mat.add_element('N', 3.2269e-05) +mat.add_element('O', 8.6569e-06) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/geometry.xml new file mode 100644 index 0000000..a11fdbc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/geometry.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/materials.xml new file mode 100644 index 0000000..46bf26d --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/materials.xml @@ -0,0 +1,42 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/settings.xml new file mode 100644 index 0000000..5fff893 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 30. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..65d786f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 8.4356e-07) +mat.add_nuclide('U235', 7.7120e-05) +mat.add_nuclide('U238', 4.3338e-06) +mat.add_element('F', 1.6459e-04) +mat.add_element('O', 3.3172e-02) +mat.add_nuclide('H2', 6.5354e-02) +mat.add_nuclide('H1', 6.6014e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Dry Air" +mat.set_density('sum') +mat.add_element('N', 3.2269e-05) +mat.add_element('O', 8.6569e-06) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/geometry.xml new file mode 100644 index 0000000..807e760 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/geometry.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/materials.xml new file mode 100644 index 0000000..26d45b9 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/materials.xml @@ -0,0 +1,42 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/settings.xml new file mode 100644 index 0000000..5fff893 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 30. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..2d8baea --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 8.4356e-07) +mat.add_nuclide('U235', 7.7120e-05) +mat.add_nuclide('U238', 4.3338e-06) +mat.add_element('F', 1.6459e-04) +mat.add_element('O', 3.3172e-02) +mat.add_nuclide('H2', 6.5354e-02) +mat.add_nuclide('H1', 6.6014e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Dry Air" +mat.set_density('sum') +mat.add_element('N', 3.2269e-05) +mat.add_element('O', 8.6569e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_element('Al', 6.0262e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/geometry.xml new file mode 100644 index 0000000..139097a --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/geometry.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/materials.xml new file mode 100644 index 0000000..4e912d7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/materials.xml @@ -0,0 +1,46 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/settings.xml new file mode 100644 index 0000000..5fff893 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 30. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..23c7a42 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2F2/D2O Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.4751e-07) +mat.add_nuclide('U235', 3.1770e-05) +mat.add_nuclide('U238', 1.7853e-06) +mat.add_element('F', 6.7806e-05) +mat.add_element('O', 3.3125e-02) +mat.add_nuclide('H2', 6.5453e-02) +mat.add_nuclide('H1', 6.6114e-04) +mat.add_s_alpha_beta('c_D_in_D2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "321 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.6511e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mat.add_element('Si', 1.6982e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Dry Air" +mat.set_density('sum') +mat.add_element('N', 3.2269e-05) +mat.add_element('O', 8.6569e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_element('Al', 6.0262e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-5/geometry.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/geometry.xml new file mode 100644 index 0000000..55db3a0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/geometry.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-5/materials.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/materials.xml new file mode 100644 index 0000000..7fcb99b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/materials.xml @@ -0,0 +1,46 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-020/openmc/case-5/settings.xml b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/settings.xml new file mode 100644 index 0000000..5fff893 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-020/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 30. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-032/mcdc/heu-sol-therm-032.py b/icsbep/openmc/heu-sol-therm-032/mcdc/heu-sol-therm-032.py new file mode 100644 index 0000000..2e41cd0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-032/mcdc/heu-sol-therm-032.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',3.9124e-09], + ['U235',3.6157e-05], + ['U238',1.9878e-06], + ['N14',0.00011212], + ['H1',0.066409], + ['O16',0.033588265220999995], + ['O17',1.2734778999999998e-05]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.011, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.786, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-032/openmc/generate_materials.py b/icsbep/openmc/heu-sol-therm-032/openmc/generate_materials.py new file mode 100644 index 0000000..a0504bb --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-032/openmc/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 3.9124e-09) +mat.add_nuclide('U234', 4.0905e-07) +mat.add_nuclide('U235', 3.6157e-05) +mat.add_nuclide('U236', 2.0858e-07) +mat.add_nuclide('U238', 1.9878e-06) +mat.add_nuclide('N14', 1.1212e-04) +mat.add_nuclide('H1', 6.6409e-02) +mat.add_element('O', 3.3601e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-032/openmc/geometry.xml b/icsbep/openmc/heu-sol-therm-032/openmc/geometry.xml new file mode 100644 index 0000000..c44c608 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-032/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-032/openmc/materials.xml b/icsbep/openmc/heu-sol-therm-032/openmc/materials.xml new file mode 100644 index 0000000..da9e377 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-032/openmc/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-032/openmc/settings.xml b/icsbep/openmc/heu-sol-therm-032/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-032/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-1.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-1.py new file mode 100644 index 0000000..4546d80 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-1.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.1337e-05], + ['U238',2.268e-06], + ['N14',0.00012716], + ['H1',0.066231], + ['O16',0.033553278485999996], + ['O17',1.2721514e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.3684, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.6986, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.3302, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=45.1358, bc='interface') +s6 = mcdc.surface('plane-z', z=304.8, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-2.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-2.py new file mode 100644 index 0000000..48507d0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-2.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.0568e-05], + ['U238',2.338e-06], + ['N14',0.00014132], + ['H1',0.06629], + ['O16',0.033616254609], + ['O17',1.2745391000000002e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.3684, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.6986, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.3302, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=47.4472, bc='interface') +s6 = mcdc.surface('plane-z', z=304.8, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-3.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-3.py new file mode 100644 index 0000000..ac239fd --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-3.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.6438e-05], + ['U238',2.0477e-06], + ['N14',0.00011898], + ['H1',0.06631], + ['O16',0.03355727697], + ['O17',1.272303e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.3684, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.6986, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.3302, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=72.7456, bc='interface') +s6 = mcdc.surface('plane-z', z=304.8, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-4.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-4.py new file mode 100644 index 0000000..0b350cd --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-4.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.4834e-05], + ['U238',1.9615e-06], + ['N14',0.00012091], + ['H1',0.066319], + ['O16',0.033561275454], + ['O17',1.2724545999999997e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.3684, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.6986, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.3302, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=105.283, bc='interface') +s6 = mcdc.surface('plane-z', z=304.8, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-5.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-5.py new file mode 100644 index 0000000..3db4e0e --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-5.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.3509e-05], + ['U238',1.9245e-06], + ['N14',0.00012479], + ['H1',0.066293], + ['O16',0.033553278485999996], + ['O17',1.2721514e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.3684, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=77.6986, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-0.3302, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=203.3524, bc='interface') +s6 = mcdc.surface('plane-z', z=304.8, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-6.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-6.py new file mode 100644 index 0000000..1f8a55a --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-6.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.3929e-05], + ['U238',1.9749e-06], + ['N14',0.00014059], + ['H1',0.066161], + ['O16',0.033529287582], + ['O17',1.2712418000000001e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=136.779, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=138.684, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-1.905, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=90.932, bc='interface') +s6 = mcdc.surface('plane-z', z=274.32, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-7.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-7.py new file mode 100644 index 0000000..17a3338 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-7.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.318e-05], + ['U238',1.9456e-06], + ['N14',0.00013695], + ['H1',0.066369], + ['O16',0.033621252713999995], + ['O17',1.2747285999999999e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=136.779, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=138.684, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-1.905, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=122.4534, bc='interface') +s6 = mcdc.surface('plane-z', z=274.32, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-8.py b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-8.py new file mode 100644 index 0000000..80d1fbe --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/mcdc/heu-sol-therm-042_case-8.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',3.2367e-05], + ['U238',1.8936000000000002e-06], + ['N14',0.00013387], + ['H1',0.066362], + ['O16',0.033607258019999996], + ['O17',1.274198e-05]]) +# Material Name: SS-304 Tank +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00340179], + ['Fe56',0.053400828000000004], + ['Fe57',0.001233258], + ['Fe58',0.000164124], + ['C0',0.00031687], + ['Cr50',0.0006758213000000001], + ['Cr52',0.01303254106], + ['Cr53',0.00147778554], + ['Cr54',0.0003678521000000001], + ['Ni58',0.0066220442937], + ['Ni60',0.0025507996062999997], + ['Ni61',0.00011088149269999999], + ['Ni62',0.00035353871850000003], + ['Ni64',9.00358888e-05], + ['Mo100',0.00012079636800000002], + ['Mo92',0.00018160365299999998], + ['Mo94',0.00011389123899999999], + ['Mo95',0.000196777581], + ['Mo96',0.000206695181], + ['Mo97',0.000118788054], + ['Mo98',0.00030114792400000003], + ['N14',0.00033841582542], + ['N15',1.24417458e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=136.779, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=138.684, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-1.905, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=241.046, bc='interface') +s6 = mcdc.surface('plane-z', z=274.32, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c4 = mcdc.cell(-s1 & +s5 & -s6, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..ebfe0c6 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.6760e-07) +mat.add_nuclide('U235', 4.1337e-05) +mat.add_nuclide('U236', 2.4286e-07) +mat.add_nuclide('U238', 2.2680e-06) +mat.add_nuclide('N14', 1.2716e-04) +mat.add_nuclide('H1', 6.6231e-02) +mat.add_element('O', 3.3566e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/geometry.xml new file mode 100644 index 0000000..35b6172 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/materials.xml new file mode 100644 index 0000000..b350478 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..df3c506 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.5109e-07) +mat.add_nuclide('U235', 4.0568e-05) +mat.add_nuclide('U236', 2.2146e-07) +mat.add_nuclide('U238', 2.3380e-06) +mat.add_nuclide('N14', 1.4132e-04) +mat.add_nuclide('H1', 6.6290e-02) +mat.add_element('O', 3.3629e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/geometry.xml new file mode 100644 index 0000000..626a670 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/materials.xml new file mode 100644 index 0000000..28861b4 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..eb9e793 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.0870e-07) +mat.add_nuclide('U235', 3.6438e-05) +mat.add_nuclide('U236', 2.1041e-07) +mat.add_nuclide('U238', 2.0477e-06) +mat.add_nuclide('N14', 1.1898e-04) +mat.add_nuclide('H1', 6.6310e-02) +mat.add_element('O', 3.3570e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/geometry.xml new file mode 100644 index 0000000..0dcd8a6 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/materials.xml new file mode 100644 index 0000000..4e8ba20 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-4/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..935e9a7 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.9827e-07) +mat.add_nuclide('U235', 3.4834e-05) +mat.add_nuclide('U236', 1.9372e-07) +mat.add_nuclide('U238', 1.9615e-06) +mat.add_nuclide('N14', 1.2091e-04) +mat.add_nuclide('H1', 6.6319e-02) +mat.add_element('O', 3.3574e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-4/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/geometry.xml new file mode 100644 index 0000000..bd7354f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-4/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/materials.xml new file mode 100644 index 0000000..9d154ea --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-4/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-5/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..c5232e3 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8353e-07) +mat.add_nuclide('U235', 3.3509e-05) +mat.add_nuclide('U236', 1.8655e-07) +mat.add_nuclide('U238', 1.9245e-06) +mat.add_nuclide('N14', 1.2479e-04) +mat.add_nuclide('H1', 6.6293e-02) +mat.add_element('O', 3.3566e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-5/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/geometry.xml new file mode 100644 index 0000000..a181b69 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-5/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/materials.xml new file mode 100644 index 0000000..3e9d71b --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-5/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-6/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..e6b5a5f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.9660e-07) +mat.add_nuclide('U235', 3.3929e-05) +mat.add_nuclide('U236', 2.4031e-07) +mat.add_nuclide('U238', 1.9749e-06) +mat.add_nuclide('N14', 1.4059e-04) +mat.add_nuclide('H1', 6.6161e-02) +mat.add_element('O', 3.3542e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-6/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/geometry.xml new file mode 100644 index 0000000..4b30a80 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-6/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/materials.xml new file mode 100644 index 0000000..68a105f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-6/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-7/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..2bde608 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8070e-07) +mat.add_nuclide('U235', 3.3180e-05) +mat.add_nuclide('U236', 2.3146e-07) +mat.add_nuclide('U238', 1.9456e-06) +mat.add_nuclide('N14', 1.3695e-04) +mat.add_nuclide('H1', 6.6369e-02) +mat.add_element('O', 3.3634e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-7/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/geometry.xml new file mode 100644 index 0000000..47e21cd --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-7/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/materials.xml new file mode 100644 index 0000000..1b4e9b5 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-7/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-7/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-8/generate_materials.py b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..90f7089 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.6771e-07) +mat.add_nuclide('U235', 3.2367e-05) +mat.add_nuclide('U236', 2.1875e-07) +mat.add_nuclide('U238', 1.8936e-06) +mat.add_nuclide('N14', 1.3387e-04) +mat.add_nuclide('H1', 6.6362e-02) +mat.add_element('O', 3.3620e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "SS-304 Tank" +mat.set_density('sum') +mat.add_element('Fe', 5.8200e-02) +mat.add_element('C', 3.1687e-04) +mat.add_element('Cr', 1.5554e-02) +mat.add_element('Ni', 9.7273e-03) +mat.add_element('Mo', 1.2397e-03) +mat.add_element('N', 3.3966e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-8/geometry.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/geometry.xml new file mode 100644 index 0000000..19c2cae --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/geometry.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-8/materials.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/materials.xml new file mode 100644 index 0000000..9e508f0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-042/openmc/case-8/settings.xml b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-042/openmc/case-8/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-1.py b/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-1.py new file mode 100644 index 0000000..50fc542 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-1.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00032073], + ['U238',1.792e-05], + ['F19',0.00068833], + ['O16',0.033309370962], + ['O17',1.2629038e-05], + ['H1',0.065268]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.9572, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.0842, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-2.py b/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-2.py new file mode 100644 index 0000000..8ce0fa0 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-2.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.0013e-05], + ['U238',3.5985000000000004e-06], + ['F19',0.0001287], + ['O16',0.033456315249], + ['O17',1.2684751e-05], + ['H1',0.066681]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=27.9244, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=28.1244, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-3.py b/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-3.py new file mode 100644 index 0000000..b44a853 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/mcdc/heu-sol-therm-043_case-3.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.7739e-05], + ['U238',2.8625e-06], + ['F19',0.00010237999999999999], + ['O16',0.033319367172], + ['O17',1.2632828e-05], + ['H1',0.066459]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.5948, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.9148, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-1/generate_materials.py b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..f5e8da1 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8045e-06) +mat.add_nuclide('U235', 3.2073e-04) +mat.add_nuclide('U236', 1.7146e-06) +mat.add_nuclide('U238', 1.7920e-05) +mat.add_nuclide('F19', 6.8833e-04) +mat.add_element('O', 3.3322e-02) +mat.add_nuclide('H1', 6.5268e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-1/geometry.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/geometry.xml new file mode 100644 index 0000000..1cbe328 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-1/materials.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/materials.xml new file mode 100644 index 0000000..13a9418 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-1/settings.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-2/generate_materials.py b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..6d03c68 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 7.3720e-07) +mat.add_nuclide('U235', 6.0013e-05) +mat.add_nuclide('U238', 3.5985e-06) +mat.add_nuclide('F19', 1.2870e-04) +mat.add_element('O', 3.3469e-02) +mat.add_nuclide('H1', 6.6681e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-2/geometry.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/geometry.xml new file mode 100644 index 0000000..b65a538 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-2/materials.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/materials.xml new file mode 100644 index 0000000..4dd902f --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/materials.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-2/settings.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-3/generate_materials.py b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..4b046c8 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.8643e-07) +mat.add_nuclide('U235', 4.7739e-05) +mat.add_nuclide('U238', 2.8625e-06) +mat.add_nuclide('F19', 1.0238e-04) +mat.add_element('O', 3.3332e-02) +mat.add_nuclide('H1', 6.6459e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-3/geometry.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/geometry.xml new file mode 100644 index 0000000..789eb19 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-3/materials.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/materials.xml new file mode 100644 index 0000000..11dff65 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/materials.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/heu-sol-therm-043/openmc/case-3/settings.xml b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/settings.xml new file mode 100644 index 0000000..03fab75 --- /dev/null +++ b/icsbep/openmc/heu-sol-therm-043/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + point + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/icsbep/__init__.py b/icsbep/openmc/icsbep/__init__.py new file mode 100644 index 0000000..e69de29 diff --git a/icsbep/openmc/icsbep/icsbep.py b/icsbep/openmc/icsbep/icsbep.py new file mode 100644 index 0000000..f7144e6 --- /dev/null +++ b/icsbep/openmc/icsbep/icsbep.py @@ -0,0 +1,14 @@ +import csv +import os + +cwd = os.path.dirname(os.path.realpath(__file__)) + +model_keff = {} +with open(os.path.join(cwd, 'uncertainties.csv'), 'r') as csvfile: + reader = csv.reader(csvfile, skipinitialspace=True) + for benchmark, case, mean, uncertainty in reader: + if case: + name = '{}/{}'.format(benchmark, case) + else: + name = benchmark + model_keff[name] = (float(mean), float(uncertainty)) diff --git a/icsbep/openmc/ieu-comp-fast-001/mcdc/ieu-comp-fast-001.py b/icsbep/openmc/ieu-comp-fast-001/mcdc/ieu-comp-fast-001.py new file mode 100644 index 0000000..ada37a5 --- /dev/null +++ b/icsbep/openmc/ieu-comp-fast-001/mcdc/ieu-comp-fast-001.py @@ -0,0 +1,343 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Inner Core 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00115084], + ['U238',0.00579612], + ['C0',4.97945e-05], + ['Cl35',2.9745448514099998e-06], + ['Cl37',9.5148514859e-07], + ['Co59',8.32631e-07], + ['Cr50',0.0001226632605], + ['Cr52',0.0023654388801], + ['Cr53',0.00026822178089999996], + ['Cr54',6.67660785e-05], + ['Cu63',1.84620819e-05], + ['Cu65',8.236518099999999e-06], + ['F19',1.07411e-05], + ['Fe54',0.000781295305], + ['Fe56',0.012264665426], + ['Fe57',0.000283244611], + ['Fe58',3.7694657999999995e-05], + ['H1',2.0784662492454002e-06], + ['H2',3.237507546e-10], + ['Mn55',0.000234499], + ['Mo100',1.387214304e-06], + ['Mo92',2.085519534e-06], + ['Mo94',1.307916442e-06], + ['Mo95',2.2597755180000003e-06], + ['Mo96',2.373668318e-06], + ['Mo97',1.364151012e-06], + ['Mo98',3.458354872e-06], + ['Na23',0.00927752], + ['Ni58',0.0008343368710199999], + ['Ni60',0.00032138506898], + ['Ni61',1.3970386419999997e-05], + ['Ni62',4.4543705100000004e-05], + ['Ni64',1.1343968480000001e-05], + ['O16',0.0137473877646], + ['O17',5.2122354e-06], + ['Si28',0.00014479875300639998], + ['Si29',7.352467536800001e-06], + ['Si30',4.8467794568e-06], + ['Al27',2.87511e-06]]) +# Material Name: Outer Core 1 +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.0011439], + ['U238',0.00579503], + ['C0',4.73406e-05], + ['Cl35',2.7926110773e-06], + ['Cl37',8.932889227000001e-07], + ['Co59',2.58295e-07], + ['Cr50',0.000122766237], + ['Cr52',0.0023674246794], + ['Cr53',0.0002684469546], + ['Cr54',6.6822129e-05], + ['Cu63',1.857369e-05], + ['Cu65',8.28631e-06], + ['F19',1.00311e-05], + ['Fe54',0.00080694901], + ['Fe56',0.012667373731999998], + ['Fe57',0.000292544902], + ['Fe58',3.8932356e-05], + ['H1',1.9282396491804e-06], + ['H2',3.003508196e-10], + ['Mn55',0.00023366299999999998], + ['Mo100',1.462272336e-06], + ['Mo92',2.1983607810000003e-06], + ['Mo94',1.378683903e-06], + ['Mo95',2.3820452370000003e-06], + ['Mo96',2.502100437e-06], + ['Mo97',1.437961158e-06], + ['Mo98',3.645476148e-06], + ['Na23',0.00916324], + ['Ni58',0.0008311304490299999], + ['Ni60',0.00032014996096999996], + ['Ni61',1.391669713e-05], + ['Ni62',4.4372520150000005e-05], + ['Ni64',1.130037272e-05], + ['O16',0.0143039767374], + ['O17',5.4232626e-06], + ['Si28',0.0001391183270152], + ['Si29',7.0640317124e-06], + ['Si30',4.6566412724e-06], + ['Al27',2.45958e-06]]) +# Material Name: Inner Axial reflector 1 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',8.27435e-05], + ['U238',0.0372332], + ['C0',3.6713e-05], + ['Cl35',2.3028832094399997e-06], + ['Cl37',7.366367905600001e-07], + ['Cr50',6.3366611e-05], + ['Cr52',0.0012219620182], + ['Cr53',0.0001385606838], + ['Cr54',3.4490687e-05], + ['Cu63',1.27353555e-05], + ['Cu65',5.6816445e-06], + ['F19',9.00934e-06], + ['Fe54',0.000313057031], + ['Fe56',0.0049143258892], + ['Fe57',0.00011349321619999999], + ['Fe58',1.51038636e-05], + ['H1',1.7847220040999999e-06], + ['H2',2.779959e-10], + ['Mn55',0.000127853], + ['Mo100',9.093695184e-07], + ['Mo92',1.3671340389e-06], + ['Mo94',8.573868807e-07], + ['Mo95',1.4813651853000002e-06], + ['Mo96',1.5560260652999998e-06], + ['Mo97',8.942506902000001e-07], + ['Mo98',2.2670776212e-06], + ['Ni58',0.0004067594775], + ['Ni60',0.0001566830225], + ['Ni61',6.8109025e-06], + ['Ni62',2.1716137500000003e-05], + ['Ni64',5.53046e-06], + ['Si28',8.007915749744e-05], + ['Si29',4.06619113528e-06], + ['Si30',2.6804513672799997e-06]]) +# Material Name: Outer Axial Reflector 1 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',8.25608e-05], + ['U238',0.0371671], + ['C0',3.7323e-05], + ['Cl35',2.5286695919099996e-06], + ['Cl37',8.0886040809e-07], + ['Cr50',6.3765482e-05], + ['Cr52',0.0012296538484], + ['Cr53',0.0001394328756], + ['Cr54',3.4707794e-05], + ['Cu63',1.27881861e-05], + ['Cu65',5.7052139e-06], + ['F19',9.89177e-06], + ['Fe54',0.0003148648895], + ['Fe56',0.0049427054014], + ['Fe57',0.00011414862290000002], + ['Fe58',1.5191086199999998e-05], + ['H1',1.9552054488726e-06], + ['H2',3.0455112739999997e-10], + ['Mn55',0.000128517], + ['Mo100',9.150288335999999e-07], + ['Mo92',1.3756421781000002e-06], + ['Mo94',8.627226903000001e-07], + ['Mo95',1.4905842237000001e-06], + ['Mo96',1.5657097437000003e-06], + ['Mo97',8.998159158000001e-07], + ['Mo98',2.2811864148e-06], + ['Ni58',0.000409415157369], + ['Ni60',0.000157705985631], + ['Ni61',6.855369999e-06], + ['Ni62',2.1857919345e-05], + ['Ni64',5.566567656000001e-06], + ['Si28',8.022331248728e-05], + ['Si29',4.07351091436e-06], + ['Si30',2.68527659836e-06]]) +# Material Name: Inner Axial reflector 2 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',8.65264e-05], + ['U238',0.0387479], + ['C0',1.87415e-05], + ['Cr50',5.166596050000001e-05], + ['Cr52',0.0009963266201], + ['Cr53',0.0001129754409], + ['Cr54',2.81219785e-05], + ['Cu63',1.1915858850000001e-05], + ['Cu65',5.31604115e-06], + ['Fe54',0.000250115733], + ['Fe56',0.0039262821156], + ['Fe57',9.06749766e-05], + ['Fe58',1.20671748e-05], + ['Mn55',0.000105905], + ['Mo100',8.045162832e-07], + ['Mo92',1.2094990797e-06], + ['Mo94',7.585274110999999e-07], + ['Mo95',1.3105590069000002e-06], + ['Mo96',1.3766112468999996e-06], + ['Mo97',7.911407045999999e-07], + ['Mo98',2.0056762676e-06], + ['Ni58',0.000326888254575], + ['Ni60',0.000125916770425], + ['Ni61',5.473514825e-06], + ['Ni62',1.7451960375e-05], + ['Ni64',4.4444998000000005e-06], + ['Si28',6.30025555564e-05], + ['Si29',3.1990900118e-06], + ['Si30',2.1088544318e-06]]) +# Material Name: Outer Axial Reflector 2 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',8.57702e-05], + ['U238',0.0384184], + ['C0',1.92861e-05], + ['Cl35',1.22901708105e-07], + ['Cl37',3.9313291895e-08], + ['Cr50',5.2437632500000007e-05], + ['Cr52',0.0010112075465], + ['Cr53',0.00011466281849999998], + ['Cr54',2.8542002499999996e-05], + ['Cu63',1.201087095e-05], + ['Cu65',5.3584290499999995e-06], + ['F19',4.80817e-07], + ['Fe54',0.000253782886], + ['Fe56',0.0039838485752], + ['Fe57',9.200443720000001e-05], + ['Fe58',1.2244101600000001e-05], + ['H1',9.524846369365801e-08], + ['H2',1.4836306342e-11], + ['Mn55',0.000107236], + ['Mo100',8.190650495999999e-07], + ['Mo92',1.2313715016e-06], + ['Mo94',7.722445207999999e-07], + ['Mo95',1.3342589832e-06], + ['Mo96',1.4015057031999998e-06], + ['Mo97',8.054475888000001e-07], + ['Mo98',2.0419466528e-06], + ['Ni58',0.000332019210528], + ['Ni60',0.000127893205472], + ['Ni61',5.559429088e-06], + ['Ni62',1.7725892640000003e-05], + ['Ni64',4.5142622720000005e-06], + ['Si28',6.352881811048e-05], + ['Si29',3.2258121227599997e-06], + ['Si30',2.12646976676e-06]]) +# Material Name: Radial Reflector 1 & 2 +# Depletable +m8 = mcdc.material(nuclides=[ + ['U235',8.66555e-05], + ['U238',0.0388076], + ['C0',1.85721e-05], + ['Cr50',5.11932245e-05], + ['Cr52',0.0009872103769], + ['Cr53',0.0001119417321], + ['Cr54',2.7864666500000006e-05], + ['Cu63',1.1807224200000002e-05], + ['Cu65',5.2675758000000005e-06], + ['Fe54',0.000247826831], + ['Fe56',0.0038903512492], + ['Fe57',8.98451762e-05], + ['Fe58',1.19567436e-05], + ['Mn55',0.000104936], + ['Mo100',7.971917184e-07], + ['Mo92',1.1984874264e-06], + ['Mo94',7.516215432e-07], + ['Mo95',1.2986272728000002e-06], + ['Mo96',1.3640781528e-06], + ['Mo97',7.839379152e-07], + ['Mo98',1.9874159712e-06], + ['Ni58',0.00032389627482], + ['Ni60',0.00012476426518], + ['Ni61',5.42341622e-06], + ['Ni62',1.72922241e-05], + ['Ni64',4.40381968e-06], + ['Si28',6.242547444864e-05], + ['Si29',3.1697874796800003e-06], + ['Si30',2.08953807168e-06]]) +# Material Name: Empty Matrix +m10 = mcdc.material(nuclides=[ + ['C0',1.86434e-05], + ['Cr50',5.140786750000001e-05], + ['Cr52',0.0009913495535], + ['Cr53',0.00011241108149999999], + ['Cr54',2.7981497499999996e-05], + ['Cu63',1.1848852500000001e-05], + ['Cu65',5.2861475e-06], + ['Fe54',0.0002488608115], + ['Fe56',0.0039065825318], + ['Fe57',9.02200273e-05], + ['Fe58',1.20066294e-05], + ['Mn55',0.000105352], + ['Mo100',8.008281792e-07], + ['Mo92',1.2039544332000002e-06], + ['Mo94',7.550501315999998e-07], + ['Mo95',1.3045510764e-06], + ['Mo96',1.3703005163999999e-06], + ['Mo97',7.875139175999999e-07], + ['Mo98',1.9964817456e-06], + ['Ni58',0.000325280958966], + ['Ni60',0.000125297643034], + ['Ni61',5.446601786e-06], + ['Ni62',1.7366149830000003e-05], + ['Ni64',4.422646384e-06], + ['Si28',6.2651621624e-05], + ['Si29',3.181270588e-06], + ['Si30',2.0971077879999997e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=24.3435, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=91.2449, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=119.9487, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=140.2589, bc='vacuum') +s5 = mcdc.surface('plane-z', z=0.0, bc='reflective') +s6 = mcdc.surface('plane-z', z=76.2813, bc='interface') +s7 = mcdc.surface('plane-z', z=101.7257, bc='interface') +s8 = mcdc.surface('plane-z', z=106.68, bc='interface') +s9 = mcdc.surface('plane-z', z=110.4544, bc='interface') +s10 = mcdc.surface('plane-z', z=121.92, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & +s5 & -s6, fill=m1) +c2 = mcdc.cell(+s1 & -s2 & +s5 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s6 & -s7, fill=m4) +c4 = mcdc.cell(+s1 & -s2 & +s6 & -s7, fill=m5) +c5 = mcdc.cell(-s1 & +s7 & -s9, fill=m6) +c6 = mcdc.cell(+s1 & -s2 & +s7 & -s9, fill=m7) +c7 = mcdc.cell(+s2 & -s3 & +s5 & -s8, fill=m8) +c8 = mcdc.cell(+s2 & -s3 & +s8 & -s9, fill=m8) +c9 = mcdc.cell(-s3 & +s9 & -s10, fill=m10) +c10 = mcdc.cell(+s3 & -s4 & +s5 & -s10, fill=m10) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-141.0,141.0], y=[-141.0,141.0], z=[0.0,122.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-comp-fast-001/openmc/generate_materials.py b/icsbep/openmc/ieu-comp-fast-001/openmc/generate_materials.py new file mode 100644 index 0000000..e570c28 --- /dev/null +++ b/icsbep/openmc/ieu-comp-fast-001/openmc/generate_materials.py @@ -0,0 +1,150 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Inner Core 1" +mat.set_density('sum') +mat.add_nuclide('U234', 1.12777E-05) +mat.add_nuclide('U235', 1.15084E-03) +mat.add_nuclide('U236', 5.40689E-06) +mat.add_nuclide('U238', 5.79612E-03) +mat.add_element('C', 4.97945E-05) +mat.add_element('Cl', 3.92603E-06) +mat.add_element('Co', 8.32631E-07) +mat.add_element('Cr', 2.82309E-03) +mat.add_element('Cu', 2.66986E-05) +mat.add_element('F', 1.07411E-05) +mat.add_element('Fe', 1.33669E-02) +mat.add_element('H', 2.07879E-06) +mat.add_element('Mn', 2.34499E-04) +mat.add_element('Mo', 1.42366E-05) +mat.add_element('Na', 9.27752E-03) +mat.add_element('Ni', 1.22558E-03) +mat.add_element('O', 1.37526E-02) +mat.add_element('Si', 1.56998E-04) +mat.add_element('Al', 2.87511E-06) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Outer Core 1" +mat.set_density('sum') +mat.add_nuclide('U234', 1.11611E-05) +mat.add_nuclide('U235', 1.14390E-03) +mat.add_nuclide('U236', 5.35052E-06) +mat.add_nuclide('U238', 5.79503E-03) +mat.add_element('C', 4.73406E-05) +mat.add_element('Cl', 3.68590E-06) +mat.add_element('Co', 2.58295E-07) +mat.add_element('Cr', 2.82546E-03) +mat.add_element('Cu', 2.68600E-05) +mat.add_element('F', 1.00311E-05) +mat.add_element('Fe', 1.38058E-02) +mat.add_element('H', 1.92854E-06) +mat.add_element('Mn', 2.33663E-04) +mat.add_element('Mo', 1.50069E-05) +mat.add_element('Na', 9.16324E-03) +mat.add_element('Ni', 1.22087E-03) +mat.add_element('O', 1.43094E-02) +mat.add_element('Si', 1.50839E-04) +mat.add_element('Al', 2.45958E-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Inner Axial reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.27435E-05) +mat.add_nuclide('U238', 3.72332E-02) +mat.add_element('C', 3.67130E-05) +mat.add_element('Cl', 3.03952E-06) +mat.add_element('Cr', 1.45838E-03) +mat.add_element('Cu', 1.84170E-05) +mat.add_element('F', 9.00934E-06) +mat.add_element('Fe', 5.35598E-03) +mat.add_element('H', 1.78500E-06) +mat.add_element('Mn', 1.27853E-04) +mat.add_element('Mo', 9.33261E-06) +mat.add_element('Ni', 5.97500E-04) +mat.add_element('Si', 8.68258E-05) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Inner Axial reflector 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.65264E-05) +mat.add_nuclide('U238', 3.87479E-02) +mat.add_element('C', 1.87415E-05) +mat.add_element('Cr', 1.18909E-03) +mat.add_element('Cu', 1.72319E-05) +mat.add_element('Fe', 4.27914E-03) +mat.add_element('Mn', 1.05905E-04) +mat.add_element('Mo', 8.25653E-06) +mat.add_element('Ni', 4.80175E-04) +mat.add_element('Si', 6.83105E-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Outer Axial Reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.25608E-05) +mat.add_nuclide('U238', 3.71671E-02) +mat.add_element('C', 3.73230E-05) +mat.add_element('Cl', 3.33753E-06) +mat.add_element('Cr', 1.46756E-03) +mat.add_element('Cu', 1.84934E-05) +mat.add_element('F', 9.89177E-06) +mat.add_element('Fe', 5.38691E-03) +mat.add_element('H', 1.95551E-06) +mat.add_element('Mn', 1.28517E-04) +mat.add_element('Mo', 9.39069E-06) +mat.add_element('Ni', 6.01401E-04) +mat.add_element('Si', 8.69821E-05) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Outer Axial Reflector 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.57702E-05) +mat.add_nuclide('U238', 3.84184E-02) +mat.add_element('C', 1.92861E-05) +mat.add_element('Cl', 1.62215E-07) +mat.add_element('Cr', 1.20685E-03) +mat.add_element('Cu', 1.73693E-05) +mat.add_element('F', 4.80817E-07) +mat.add_element('Fe', 4.34188E-03) +mat.add_element('H', 9.52633E-08) +mat.add_element('Mn', 1.07236E-04) +mat.add_element('Mo', 8.40584E-06) +mat.add_element('Ni', 4.87712E-04) +mat.add_element('Si', 6.88811E-05) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Radial Reflector 1 & 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.66555E-05) +mat.add_nuclide('U238', 3.88076E-02) +mat.add_element('C', 1.85721E-05) +mat.add_element('Cr', 1.17821E-03) +mat.add_element('Cu', 1.70748E-05) +mat.add_element('Fe', 4.23998E-03) +mat.add_element('Mn', 1.04936E-04) +mat.add_element('Mo', 8.18136E-06) +mat.add_element('Ni', 4.75780E-04) +mat.add_element('Si', 6.76848E-05) +mats.append(mat) + +mat = openmc.Material(10) +mat.name = "Empty Matrix" +mat.set_density('sum') +mat.add_element('C', 1.86434E-05) +mat.add_element('Cr', 1.18315E-03) +mat.add_element('Cu', 1.71350E-05) +mat.add_element('Fe', 4.25767E-03) +mat.add_element('Mn', 1.05352E-04) +mat.add_element('Mo', 8.21868E-06) +mat.add_element('Ni', 4.77814E-04) +mat.add_element('Si', 6.79300E-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-comp-fast-001/openmc/geometry.xml b/icsbep/openmc/ieu-comp-fast-001/openmc/geometry.xml new file mode 100644 index 0000000..5f1868f --- /dev/null +++ b/icsbep/openmc/ieu-comp-fast-001/openmc/geometry.xml @@ -0,0 +1,52 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-comp-fast-001/openmc/materials.xml b/icsbep/openmc/ieu-comp-fast-001/openmc/materials.xml new file mode 100644 index 0000000..893dc89 --- /dev/null +++ b/icsbep/openmc/ieu-comp-fast-001/openmc/materials.xml @@ -0,0 +1,296 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-comp-fast-001/openmc/settings.xml b/icsbep/openmc/ieu-comp-fast-001/openmc/settings.xml new file mode 100644 index 0000000..591e8be --- /dev/null +++ b/icsbep/openmc/ieu-comp-fast-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -141. -141. 0. 141. 141. 122. + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-1.py b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-1.py new file mode 100644 index 0000000..61611be --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-1.py @@ -0,0 +1,157 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Tuballoy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034591], + ['U238',0.047694]]) +# Material Name: Oralloy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044824], + ['U238',0.0026391]]) +# Material Name: Mixed Uranium +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.023353], + ['U238',0.021939]]) +# Material Name: 2024 Aluminum +m4 = mcdc.material(nuclides=[ + ['Mg24',0.0008128005450000001], + ['Mg25',0.0001031559], + ['Mg26',0.000113543555], + ['Al27',0.057868], + ['Mn55',0.00015182], + ['Cu63',0.0007986825], + ['Cu65',0.0003563175]]) +# Material Name: Stainless Steel +m5 = mcdc.material(nuclides=[ + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.11125, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.74625, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.60375, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.065, bc='interface') +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.66939, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.7, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.335, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.67711, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.29416, bc='interface') +s18 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.82055, bc='interface') +s19 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=17.1965, bc='interface') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.22627, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=21.0, bc='vacuum') +s101 = mcdc.surface('plane-z', z=0.0, bc='interface') +s105 = mcdc.surface('plane-z', z=0.804, bc='interface') +s106 = mcdc.surface('plane-z', z=1.408, bc='interface') +s109 = mcdc.surface('plane-z', z=2.212, bc='interface') +s110 = mcdc.surface('plane-z', z=2.816, bc='interface') +s113 = mcdc.surface('plane-z', z=3.62, bc='interface') +s114 = mcdc.surface('plane-z', z=4.224, bc='interface') +s117 = mcdc.surface('plane-z', z=5.028, bc='interface') +s118 = mcdc.surface('plane-z', z=5.632, bc='interface') +s121 = mcdc.surface('plane-z', z=6.436, bc='interface') +s122 = mcdc.surface('plane-z', z=7.04, bc='interface') +s125 = mcdc.surface('plane-z', z=7.844, bc='interface') +s126 = mcdc.surface('plane-z', z=8.448, bc='interface') +s129 = mcdc.surface('plane-z', z=9.252, bc='interface') +s131 = mcdc.surface('plane-z', z=9.856, bc='interface') +s134 = mcdc.surface('plane-z', z=10.66, bc='interface') +s136 = mcdc.surface('plane-z', z=11.264, bc='interface') +s138 = mcdc.surface('plane-z', z=12.068, bc='interface') +s140 = mcdc.surface('plane-z', z=12.672, bc='interface') +s142 = mcdc.surface('plane-z', z=13.476, bc='interface') +s144 = mcdc.surface('plane-z', z=14.08, bc='interface') +s146 = mcdc.surface('plane-z', z=14.884, bc='interface') +s161 = mcdc.surface('plane-z', z=14.9631, bc='vacuum') +s201 = mcdc.surface('plane-z', z=-0.3175, bc='interface') +s202 = mcdc.surface('plane-z', z=-0.9525, bc='interface') +s203 = mcdc.surface('plane-z', z=-3.175, bc='interface') +s204 = mcdc.surface('plane-z', z=-4.7625, bc='interface') +s205 = mcdc.surface('plane-z', z=-6.0325, bc='interface') +s206 = mcdc.surface('plane-z', z=-8.5725, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s101 & -s129 & -s2, fill=m3) +c51 = mcdc.cell(+s101 & -s105 & +s2 & -s12, fill=m2) +c52 = mcdc.cell(+s105 & -s106 & +s2 & -s12, fill=m1) +c53 = mcdc.cell(+s106 & -s109 & +s2 & -s12, fill=m2) +c54 = mcdc.cell(+s109 & -s110 & +s2 & -s12, fill=m1) +c55 = mcdc.cell(+s110 & -s113 & +s2 & -s12, fill=m2) +c56 = mcdc.cell(+s113 & -s114 & +s2 & -s12, fill=m1) +c57 = mcdc.cell(+s114 & -s117 & +s2 & -s12, fill=m2) +c58 = mcdc.cell(+s117 & -s118 & +s2 & -s12, fill=m1) +c59 = mcdc.cell(+s118 & -s121 & +s2 & -s12, fill=m2) +c60 = mcdc.cell(+s121 & -s122 & +s2 & -s12, fill=m1) +c61 = mcdc.cell(+s122 & -s125 & +s2 & -s12, fill=m2) +c62 = mcdc.cell(+s125 & -s126 & +s2 & -s12, fill=m1) +c63 = mcdc.cell(+s126 & -s129 & +s2 & -s12, fill=m2) +c64 = mcdc.cell(+s129 & -s131 & -s10, fill=m1) +c65 = mcdc.cell(+s131 & -s134 & -s12, fill=m2) +c66 = mcdc.cell(+s134 & -s136 & -s12, fill=m1) +c67 = mcdc.cell(+s136 & -s138 & -s12, fill=m2) +c68 = mcdc.cell(+s138 & -s140 & -s12, fill=m1) +c69 = mcdc.cell(+s140 & -s142 & -s12, fill=m2) +c70 = mcdc.cell(+s142 & -s144 & -s12, fill=m1) +c71 = mcdc.cell(+s144 & -s146 & -s12, fill=m2) +c72 = mcdc.cell(+s146 & -s161 & -s12, fill=m1) +c103 = mcdc.cell(+s129 & -s131 & +s10 & -s17, fill=m4) +c106 = mcdc.cell(+s201 & -s101 & -s8, fill=mvoid) +c107 = mcdc.cell(+s202 & -s201 & +s3 & -s8, fill=mvoid) +c108 = mcdc.cell(+s202 & -s101 & +s8 & -s18, fill=m4) +c110 = mcdc.cell(+s203 & -s201 & -s3, fill=m4) +c111 = mcdc.cell(+s205 & -s203 & -s7, fill=m4) +c112 = mcdc.cell(+s204 & -s202 & +s12 & -s14, fill=m4) +c114 = mcdc.cell(+s204 & -s202 & +s14 & -s21, fill=mvoid) +c118 = mcdc.cell(+s205 & -s204 & +s11 & -s19, fill=m4) +c119 = mcdc.cell(+s205 & -s204 & +s7 & -s11, fill=mvoid) +c120 = mcdc.cell(+s206 & -s205 & -s20, fill=m5) +c122 = mcdc.cell(+s205 & -s204 & +s19 & -s21, fill=mvoid) +c123 = mcdc.cell(+s206 & -s205 & +s20 & -s21, fill=mvoid) +c113 = mcdc.cell(+s3 & -s12 & -s202 & +s203, fill=mvoid) +c1132 = mcdc.cell(-s203 & -s12 & +s204 & +s7, fill=mvoid) +c121 = mcdc.cell(-s21 & +s17 & -s161 & +s202, fill=mvoid) +c124 = mcdc.cell(-s161 & +s131 & +s12 & -s17, fill=mvoid) +c125 = mcdc.cell(+s12 & -s129 & -s17 & +s101, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-2.py b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-2.py new file mode 100644 index 0000000..0790c61 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-2.py @@ -0,0 +1,152 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Tuballoy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034597], + ['U238',0.047702]]) +# Material Name: Oralloy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044825], + ['U238',0.0026391]]) +# Material Name: 2024 Aluminum +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0008128005450000001], + ['Mg25',0.0001031559], + ['Mg26',0.000113543555], + ['Al27',0.057868], + ['Mn55',0.00015182], + ['Cu63',0.0007986825], + ['Cu65',0.0003563175]]) +# Material Name: Stainless Steel +m4 = mcdc.material(nuclides=[ + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.11125, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.74625, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.60375, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.065, bc='interface') +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.66939, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.7, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.335, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.67711, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.29416, bc='interface') +s18 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.82055, bc='interface') +s19 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=17.1965, bc='interface') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.22627, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=21.0, bc='vacuum') +s101 = mcdc.surface('plane-z', z=0.0, bc='interface') +s105 = mcdc.surface('plane-z', z=0.804, bc='interface') +s106 = mcdc.surface('plane-z', z=1.408, bc='interface') +s109 = mcdc.surface('plane-z', z=2.212, bc='interface') +s110 = mcdc.surface('plane-z', z=2.816, bc='interface') +s113 = mcdc.surface('plane-z', z=3.62, bc='interface') +s114 = mcdc.surface('plane-z', z=4.224, bc='interface') +s117 = mcdc.surface('plane-z', z=5.028, bc='interface') +s118 = mcdc.surface('plane-z', z=5.632, bc='interface') +s121 = mcdc.surface('plane-z', z=6.436, bc='interface') +s122 = mcdc.surface('plane-z', z=7.04, bc='interface') +s125 = mcdc.surface('plane-z', z=7.844, bc='interface') +s126 = mcdc.surface('plane-z', z=8.448, bc='interface') +s129 = mcdc.surface('plane-z', z=9.252, bc='interface') +s131 = mcdc.surface('plane-z', z=9.856, bc='interface') +s134 = mcdc.surface('plane-z', z=10.66, bc='interface') +s136 = mcdc.surface('plane-z', z=11.264, bc='interface') +s138 = mcdc.surface('plane-z', z=12.068, bc='interface') +s140 = mcdc.surface('plane-z', z=12.672, bc='interface') +s142 = mcdc.surface('plane-z', z=13.476, bc='interface') +s144 = mcdc.surface('plane-z', z=14.08, bc='interface') +s146 = mcdc.surface('plane-z', z=14.884, bc='interface') +s148 = mcdc.surface('plane-z', z=15.488, bc='vacuum') +s201 = mcdc.surface('plane-z', z=-0.3175, bc='interface') +s202 = mcdc.surface('plane-z', z=-0.9525, bc='interface') +s203 = mcdc.surface('plane-z', z=-3.175, bc='interface') +s204 = mcdc.surface('plane-z', z=-4.7625, bc='interface') +s205 = mcdc.surface('plane-z', z=-6.0325, bc='interface') +s206 = mcdc.surface('plane-z', z=-8.5725, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s101 & -s148 & -s2, fill=mvoid) +c51 = mcdc.cell(+s101 & -s105 & +s2 & -s12, fill=m2) +c52 = mcdc.cell(+s105 & -s106 & +s2 & -s12, fill=m1) +c53 = mcdc.cell(+s106 & -s109 & +s2 & -s12, fill=m2) +c54 = mcdc.cell(+s109 & -s110 & +s2 & -s12, fill=m1) +c55 = mcdc.cell(+s110 & -s113 & +s2 & -s12, fill=m2) +c56 = mcdc.cell(+s113 & -s114 & +s2 & -s12, fill=m1) +c57 = mcdc.cell(+s114 & -s117 & +s2 & -s12, fill=m2) +c58 = mcdc.cell(+s117 & -s118 & +s2 & -s12, fill=m1) +c59 = mcdc.cell(+s118 & -s121 & +s2 & -s12, fill=m2) +c60 = mcdc.cell(+s121 & -s122 & +s2 & -s12, fill=m1) +c61 = mcdc.cell(+s122 & -s125 & +s2 & -s12, fill=m2) +c62 = mcdc.cell(+s125 & -s126 & +s2 & -s12, fill=m1) +c63 = mcdc.cell(+s126 & -s129 & +s2 & -s12, fill=m2) +c64 = mcdc.cell(+s129 & -s131 & +s2 & -s10, fill=m1) +c65 = mcdc.cell(+s131 & -s134 & +s2 & -s12, fill=m2) +c66 = mcdc.cell(+s134 & -s136 & +s2 & -s12, fill=m1) +c67 = mcdc.cell(+s136 & -s138 & +s2 & -s12, fill=m2) +c68 = mcdc.cell(+s138 & -s140 & +s2 & -s12, fill=m1) +c69 = mcdc.cell(+s140 & -s142 & +s2 & -s12, fill=m2) +c70 = mcdc.cell(+s142 & -s144 & +s2 & -s12, fill=m1) +c71 = mcdc.cell(+s144 & -s146 & +s2 & -s12, fill=m2) +c72 = mcdc.cell(+s146 & -s148 & +s2 & -s12, fill=m1) +c103 = mcdc.cell(+s129 & -s131 & +s10 & -s17, fill=m3) +c106 = mcdc.cell(+s201 & -s101 & -s8, fill=mvoid) +c107 = mcdc.cell(+s202 & -s201 & +s3 & -s8, fill=mvoid) +c108 = mcdc.cell(+s202 & -s101 & +s8 & -s18, fill=m3) +c110 = mcdc.cell(+s203 & -s201 & -s3, fill=m3) +c111 = mcdc.cell(+s205 & -s203 & -s7, fill=m3) +c112 = mcdc.cell(+s204 & -s202 & +s12 & -s14, fill=m3) +c114 = mcdc.cell(+s204 & -s202 & +s14 & -s21, fill=mvoid) +c118 = mcdc.cell(+s205 & -s204 & +s11 & -s19, fill=m3) +c119 = mcdc.cell(+s205 & -s204 & +s7 & -s11, fill=mvoid) +c120 = mcdc.cell(+s206 & -s205 & -s20, fill=m4) +c122 = mcdc.cell(+s205 & -s204 & +s19 & -s21, fill=mvoid) +c123 = mcdc.cell(+s206 & -s205 & +s20 & -s21, fill=mvoid) +c113 = mcdc.cell(+s3 & -s12 & -s202 & +s203, fill=mvoid) +c1132 = mcdc.cell(-s203 & -s12 & +s204 & +s7, fill=mvoid) +c121 = mcdc.cell(-s21 & +s17 & -s148 & +s202, fill=mvoid) +c124 = mcdc.cell(-s148 & +s131 & +s12 & -s17, fill=mvoid) +c125 = mcdc.cell(+s12 & -s129 & -s17 & +s101, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-3.py b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-3.py new file mode 100644 index 0000000..ed9df1a --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-3.py @@ -0,0 +1,175 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Tuballoy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034583], + ['U238',0.047684]]) +# Material Name: Oralloy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044849], + ['U238',0.0026305]]) +# Material Name: 2024 Aluminum +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0008128005450000001], + ['Mg25',0.0001031559], + ['Mg26',0.000113543555], + ['Al27',0.057868], + ['Mn55',0.00015182], + ['Cu63',0.0007986825], + ['Cu65',0.0003563175]]) +# Material Name: Stainless Steel +m4 = mcdc.material(nuclides=[ + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.74625, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.60375, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.065, bc='interface') +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.66939, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.7, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.335, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.67711, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.29416, bc='interface') +s18 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.82055, bc='interface') +s19 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=17.1965, bc='interface') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.22627, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=21.0, bc='vacuum') +s101 = mcdc.surface('plane-z', z=0.0, bc='interface') +s103 = mcdc.surface('plane-z', z=0.604, bc='interface') +s106 = mcdc.surface('plane-z', z=1.408, bc='interface') +s108 = mcdc.surface('plane-z', z=2.012, bc='interface') +s109 = mcdc.surface('plane-z', z=2.616, bc='interface') +s112 = mcdc.surface('plane-z', z=3.42, bc='interface') +s114 = mcdc.surface('plane-z', z=4.024, bc='interface') +s115 = mcdc.surface('plane-z', z=4.628, bc='interface') +s118 = mcdc.surface('plane-z', z=5.432, bc='interface') +s120 = mcdc.surface('plane-z', z=6.036, bc='interface') +s121 = mcdc.surface('plane-z', z=6.64, bc='interface') +s124 = mcdc.surface('plane-z', z=7.444, bc='interface') +s126 = mcdc.surface('plane-z', z=8.048, bc='interface') +s127 = mcdc.surface('plane-z', z=8.652, bc='interface') +s130 = mcdc.surface('plane-z', z=9.456, bc='interface') +s132 = mcdc.surface('plane-z', z=10.06, bc='interface') +s133 = mcdc.surface('plane-z', z=10.664, bc='interface') +s136 = mcdc.surface('plane-z', z=11.468, bc='interface') +s138 = mcdc.surface('plane-z', z=12.072, bc='interface') +s139 = mcdc.surface('plane-z', z=12.676, bc='interface') +s142 = mcdc.surface('plane-z', z=13.48, bc='interface') +s144 = mcdc.surface('plane-z', z=14.084, bc='interface') +s146 = mcdc.surface('plane-z', z=14.688, bc='interface') +s149 = mcdc.surface('plane-z', z=15.492, bc='interface') +s151 = mcdc.surface('plane-z', z=16.096, bc='interface') +s153 = mcdc.surface('plane-z', z=16.7, bc='interface') +s155 = mcdc.surface('plane-z', z=17.504, bc='interface') +s157 = mcdc.surface('plane-z', z=18.108, bc='interface') +s159 = mcdc.surface('plane-z', z=18.712, bc='interface') +s161 = mcdc.surface('plane-z', z=19.516, bc='interface') +s163 = mcdc.surface('plane-z', z=20.12, bc='interface') +s165 = mcdc.surface('plane-z', z=20.724, bc='interface') +s167 = mcdc.surface('plane-z', z=21.528, bc='interface') +s169 = mcdc.surface('plane-z', z=22.132, bc='interface') +s171 = mcdc.surface('plane-z', z=22.736, bc='interface') +s173 = mcdc.surface('plane-z', z=23.54, bc='interface') +s175 = mcdc.surface('plane-z', z=24.144, bc='interface') +s177 = mcdc.surface('plane-z', z=24.748, bc='interface') +s179 = mcdc.surface('plane-z', z=24.9729, bc='vacuum') +s201 = mcdc.surface('plane-z', z=-0.3175, bc='interface') +s202 = mcdc.surface('plane-z', z=-0.9525, bc='interface') +s203 = mcdc.surface('plane-z', z=-3.175, bc='interface') +s204 = mcdc.surface('plane-z', z=-4.7625, bc='interface') +s205 = mcdc.surface('plane-z', z=-6.0325, bc='interface') +s206 = mcdc.surface('plane-z', z=-8.5725, bc='vacuum') + +# Material Cell(s) +c51 = mcdc.cell(+s101 & -s103 & -s12, fill=m1) +c52 = mcdc.cell(+s103 & -s106 & -s12, fill=m2) +c53 = mcdc.cell(+s106 & -s108 & -s12, fill=m1) +c54 = mcdc.cell(+s108 & -s109 & -s12, fill=m1) +c55 = mcdc.cell(+s109 & -s112 & -s12, fill=m2) +c56 = mcdc.cell(+s112 & -s114 & -s12, fill=m1) +c57 = mcdc.cell(+s114 & -s115 & -s12, fill=m1) +c58 = mcdc.cell(+s115 & -s118 & -s12, fill=m2) +c59 = mcdc.cell(+s118 & -s120 & -s12, fill=m1) +c60 = mcdc.cell(+s120 & -s121 & -s12, fill=m1) +c61 = mcdc.cell(+s121 & -s124 & -s12, fill=m2) +c62 = mcdc.cell(+s124 & -s126 & -s12, fill=m1) +c63 = mcdc.cell(+s126 & -s127 & -s12, fill=m1) +c64 = mcdc.cell(+s127 & -s130 & -s12, fill=m2) +c65 = mcdc.cell(+s130 & -s132 & -s12, fill=m1) +c66 = mcdc.cell(+s132 & -s133 & -s12, fill=m1) +c67 = mcdc.cell(+s133 & -s136 & -s12, fill=m2) +c68 = mcdc.cell(+s136 & -s138 & -s12, fill=m1) +c69 = mcdc.cell(+s138 & -s139 & -s12, fill=m1) +c70 = mcdc.cell(+s139 & -s142 & -s12, fill=m2) +c71 = mcdc.cell(+s142 & -s144 & -s12, fill=m1) +c72 = mcdc.cell(+s144 & -s146 & -s10, fill=m1) +c73 = mcdc.cell(+s146 & -s149 & -s12, fill=m2) +c74 = mcdc.cell(+s149 & -s151 & -s12, fill=m1) +c75 = mcdc.cell(+s151 & -s153 & -s12, fill=m1) +c76 = mcdc.cell(+s153 & -s155 & -s12, fill=m2) +c77 = mcdc.cell(+s155 & -s157 & -s12, fill=m1) +c78 = mcdc.cell(+s157 & -s159 & -s12, fill=m1) +c79 = mcdc.cell(+s159 & -s161 & -s12, fill=m2) +c80 = mcdc.cell(+s161 & -s163 & -s12, fill=m1) +c81 = mcdc.cell(+s163 & -s165 & -s12, fill=m1) +c82 = mcdc.cell(+s165 & -s167 & -s12, fill=m2) +c83 = mcdc.cell(+s167 & -s169 & -s12, fill=m1) +c84 = mcdc.cell(+s169 & -s171 & -s12, fill=m1) +c85 = mcdc.cell(+s171 & -s173 & -s12, fill=m2) +c86 = mcdc.cell(+s173 & -s175 & -s12, fill=m1) +c87 = mcdc.cell(+s175 & -s177 & -s12, fill=m1) +c88 = mcdc.cell(+s177 & -s179 & -s12, fill=m1) +c103 = mcdc.cell(+s144 & -s146 & +s10 & -s17, fill=m3) +c106 = mcdc.cell(+s201 & -s101 & -s8, fill=mvoid) +c107 = mcdc.cell(+s202 & -s201 & +s3 & -s8, fill=mvoid) +c108 = mcdc.cell(+s202 & -s101 & +s8 & -s18, fill=m3) +c110 = mcdc.cell(+s203 & -s201 & -s3, fill=m3) +c111 = mcdc.cell(+s205 & -s203 & -s7, fill=m3) +c112 = mcdc.cell(+s204 & -s202 & +s12 & -s14, fill=m3) +c114 = mcdc.cell(+s204 & -s202 & +s14 & -s21, fill=mvoid) +c118 = mcdc.cell(+s205 & -s204 & +s11 & -s19, fill=m3) +c119 = mcdc.cell(+s205 & -s204 & +s7 & -s11, fill=mvoid) +c120 = mcdc.cell(+s206 & -s205 & -s20, fill=m4) +c122 = mcdc.cell(+s205 & -s204 & +s19 & -s21, fill=mvoid) +c123 = mcdc.cell(+s206 & -s205 & +s20 & -s21, fill=mvoid) +c113 = mcdc.cell(+s3 & -s12 & -s202 & +s203, fill=mvoid) +c1132 = mcdc.cell(-s203 & -s12 & +s204 & +s7, fill=mvoid) +c121 = mcdc.cell(-s21 & +s12 & -s179 & +s146, fill=mvoid) +c1212 = mcdc.cell(-s21 & +s17 & -s146 & +s144, fill=mvoid) +c1213 = mcdc.cell(-s21 & +s12 & -s144 & +s101, fill=mvoid) +c1214 = mcdc.cell(-s21 & +s18 & -s101 & +s202, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# eigenvalue = + +# Simulation Parameters diff --git a/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-4.py b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-4.py new file mode 100644 index 0000000..a67019a --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/mcdc/ieu-met-fast-001_case-4.py @@ -0,0 +1,179 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Tuballoy +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00034597], + ['U238',0.047702]]) +# Material Name: Oralloy +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044851], + ['U238',0.0026306]]) +# Material Name: 2024 Aluminum +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0008128005450000001], + ['Mg25',0.0001031559], + ['Mg26',0.000113543555], + ['Al27',0.057868], + ['Mn55',0.00015182], + ['Cu63',0.0007986825], + ['Cu65',0.0003563175]]) +# Material Name: Stainless Steel +m4 = mcdc.material(nuclides=[ + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.11125, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.74625, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=4.60375, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.065, bc='interface') +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.66939, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.7, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.335, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=13.67711, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.29416, bc='interface') +s18 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.82055, bc='interface') +s19 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=17.1965, bc='interface') +s20 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.22627, bc='vacuum') +s21 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=21.0, bc='vacuum') +s101 = mcdc.surface('plane-z', z=0.0, bc='interface') +s103 = mcdc.surface('plane-z', z=0.604, bc='interface') +s106 = mcdc.surface('plane-z', z=1.408, bc='interface') +s108 = mcdc.surface('plane-z', z=2.012, bc='interface') +s109 = mcdc.surface('plane-z', z=2.616, bc='interface') +s112 = mcdc.surface('plane-z', z=3.42, bc='interface') +s114 = mcdc.surface('plane-z', z=4.024, bc='interface') +s115 = mcdc.surface('plane-z', z=4.628, bc='interface') +s118 = mcdc.surface('plane-z', z=5.432, bc='interface') +s120 = mcdc.surface('plane-z', z=6.036, bc='interface') +s121 = mcdc.surface('plane-z', z=6.64, bc='interface') +s124 = mcdc.surface('plane-z', z=7.444, bc='interface') +s126 = mcdc.surface('plane-z', z=8.048, bc='interface') +s127 = mcdc.surface('plane-z', z=8.652, bc='interface') +s130 = mcdc.surface('plane-z', z=9.456, bc='interface') +s132 = mcdc.surface('plane-z', z=10.06, bc='interface') +s133 = mcdc.surface('plane-z', z=10.664, bc='interface') +s136 = mcdc.surface('plane-z', z=11.468, bc='interface') +s138 = mcdc.surface('plane-z', z=12.072, bc='interface') +s139 = mcdc.surface('plane-z', z=12.676, bc='interface') +s142 = mcdc.surface('plane-z', z=13.48, bc='interface') +s144 = mcdc.surface('plane-z', z=14.084, bc='interface') +s146 = mcdc.surface('plane-z', z=14.688, bc='interface') +s149 = mcdc.surface('plane-z', z=15.492, bc='interface') +s151 = mcdc.surface('plane-z', z=16.096, bc='interface') +s153 = mcdc.surface('plane-z', z=16.7, bc='interface') +s155 = mcdc.surface('plane-z', z=17.504, bc='interface') +s157 = mcdc.surface('plane-z', z=18.108, bc='interface') +s159 = mcdc.surface('plane-z', z=18.712, bc='interface') +s161 = mcdc.surface('plane-z', z=19.516, bc='interface') +s163 = mcdc.surface('plane-z', z=20.12, bc='interface') +s165 = mcdc.surface('plane-z', z=20.724, bc='interface') +s167 = mcdc.surface('plane-z', z=21.528, bc='interface') +s169 = mcdc.surface('plane-z', z=22.132, bc='interface') +s171 = mcdc.surface('plane-z', z=22.736, bc='interface') +s173 = mcdc.surface('plane-z', z=23.54, bc='interface') +s175 = mcdc.surface('plane-z', z=24.144, bc='interface') +s177 = mcdc.surface('plane-z', z=24.748, bc='interface') +s179 = mcdc.surface('plane-z', z=25.552, bc='interface') +s180 = mcdc.surface('plane-z', z=26.005, bc='vacuum') +s201 = mcdc.surface('plane-z', z=-0.3175, bc='interface') +s202 = mcdc.surface('plane-z', z=-0.9525, bc='interface') +s203 = mcdc.surface('plane-z', z=-3.175, bc='interface') +s204 = mcdc.surface('plane-z', z=-4.7625, bc='interface') +s205 = mcdc.surface('plane-z', z=-6.0325, bc='interface') +s206 = mcdc.surface('plane-z', z=-8.5725, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s101 & -s180 & -s2, fill=mvoid) +c51 = mcdc.cell(+s101 & -s103 & +s2 & -s12, fill=m1) +c52 = mcdc.cell(+s103 & -s106 & +s2 & -s12, fill=m2) +c53 = mcdc.cell(+s106 & -s108 & +s2 & -s12, fill=m1) +c54 = mcdc.cell(+s108 & -s109 & +s2 & -s12, fill=m1) +c55 = mcdc.cell(+s109 & -s112 & +s2 & -s12, fill=m2) +c56 = mcdc.cell(+s112 & -s114 & +s2 & -s12, fill=m1) +c57 = mcdc.cell(+s114 & -s115 & +s2 & -s12, fill=m1) +c58 = mcdc.cell(+s115 & -s118 & +s2 & -s12, fill=m2) +c59 = mcdc.cell(+s118 & -s120 & +s2 & -s12, fill=m1) +c60 = mcdc.cell(+s120 & -s121 & +s2 & -s12, fill=m1) +c61 = mcdc.cell(+s121 & -s124 & +s2 & -s12, fill=m2) +c62 = mcdc.cell(+s124 & -s126 & +s2 & -s12, fill=m1) +c63 = mcdc.cell(+s126 & -s127 & +s2 & -s12, fill=m1) +c64 = mcdc.cell(+s127 & -s130 & +s2 & -s12, fill=m2) +c65 = mcdc.cell(+s130 & -s132 & +s2 & -s12, fill=m1) +c66 = mcdc.cell(+s132 & -s133 & +s2 & -s12, fill=m1) +c67 = mcdc.cell(+s133 & -s136 & +s2 & -s12, fill=m2) +c68 = mcdc.cell(+s136 & -s138 & +s2 & -s12, fill=m1) +c69 = mcdc.cell(+s138 & -s139 & +s2 & -s12, fill=m1) +c70 = mcdc.cell(+s139 & -s142 & +s2 & -s12, fill=m2) +c71 = mcdc.cell(+s142 & -s144 & +s2 & -s12, fill=m1) +c72 = mcdc.cell(+s144 & -s146 & +s2 & -s10, fill=m1) +c73 = mcdc.cell(+s146 & -s149 & +s2 & -s12, fill=m2) +c74 = mcdc.cell(+s149 & -s151 & +s2 & -s12, fill=m1) +c75 = mcdc.cell(+s151 & -s153 & +s2 & -s12, fill=m1) +c76 = mcdc.cell(+s153 & -s155 & +s2 & -s12, fill=m2) +c77 = mcdc.cell(+s155 & -s157 & +s2 & -s12, fill=m1) +c78 = mcdc.cell(+s157 & -s159 & +s2 & -s12, fill=m1) +c79 = mcdc.cell(+s159 & -s161 & +s2 & -s12, fill=m2) +c80 = mcdc.cell(+s161 & -s163 & +s2 & -s12, fill=m1) +c81 = mcdc.cell(+s163 & -s165 & +s2 & -s12, fill=m1) +c82 = mcdc.cell(+s165 & -s167 & +s2 & -s12, fill=m2) +c83 = mcdc.cell(+s167 & -s169 & +s2 & -s12, fill=m1) +c84 = mcdc.cell(+s169 & -s171 & +s2 & -s12, fill=m1) +c85 = mcdc.cell(+s171 & -s173 & +s2 & -s12, fill=m2) +c86 = mcdc.cell(+s173 & -s175 & +s2 & -s12, fill=m1) +c87 = mcdc.cell(+s175 & -s177 & +s2 & -s12, fill=m1) +c88 = mcdc.cell(+s177 & -s179 & +s2 & -s12, fill=m2) +c89 = mcdc.cell(+s179 & -s180 & +s2 & -s12, fill=m1) +c103 = mcdc.cell(+s144 & -s146 & +s10 & -s17, fill=m3) +c106 = mcdc.cell(+s201 & -s101 & -s8, fill=mvoid) +c107 = mcdc.cell(+s202 & -s201 & +s3 & -s8, fill=mvoid) +c108 = mcdc.cell(+s202 & -s101 & +s8 & -s18, fill=m3) +c110 = mcdc.cell(+s203 & -s201 & -s3, fill=m3) +c111 = mcdc.cell(+s205 & -s203 & -s7, fill=m3) +c112 = mcdc.cell(+s204 & -s202 & +s12 & -s14, fill=m3) +c114 = mcdc.cell(+s204 & -s202 & +s14 & -s21, fill=mvoid) +c118 = mcdc.cell(+s205 & -s204 & +s11 & -s19, fill=m3) +c119 = mcdc.cell(+s205 & -s204 & +s7 & -s11, fill=mvoid) +c120 = mcdc.cell(+s206 & -s205 & -s20, fill=m4) +c122 = mcdc.cell(+s205 & -s204 & +s19 & -s21, fill=mvoid) +c123 = mcdc.cell(+s206 & -s205 & +s20 & -s21, fill=mvoid) +c113 = mcdc.cell(+s3 & -s12 & -s202 & +s203, fill=mvoid) +c1132 = mcdc.cell(-s203 & -s12 & +s204 & +s7, fill=mvoid) +c121 = mcdc.cell(-s21 & +s12 & -s180 & +s146, fill=mvoid) +c1212 = mcdc.cell(-s21 & +s17 & -s146 & +s144, fill=mvoid) +c1213 = mcdc.cell(-s21 & +s12 & -s144 & +s101, fill=mvoid) +c1214 = mcdc.cell(-s21 & +s18 & -s101 & +s202, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# eigenvalue = + +# Simulation Parameters diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-1/generate_materials.py b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..32213c7 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Tuballoy" +mat.set_density('sum') +mat.add_nuclide('U234', 2.6423e-06) +mat.add_nuclide('U235', 3.4591e-04) +mat.add_nuclide('U238', 4.7694e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Oralloy" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9156e-04) +mat.add_nuclide('U235', 4.4824e-02) +mat.add_nuclide('U238', 2.6391e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Mixed Uranium" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5561e-04) +mat.add_nuclide('U235', 2.3353e-02) +mat.add_nuclide('U238', 2.1939e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "2024 Aluminum" +mat.set_density('sum') +mat.add_element('Mg', 1.0295e-03) +mat.add_element('Al', 5.7868e-02) +mat.add_element('Mn', 1.5182e-04) +mat.add_element('Cu', 1.1550e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Stainless Steel" +mat.set_density('sum') +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-1/geometry.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/geometry.xml new file mode 100644 index 0000000..0d39b75 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/geometry.xml @@ -0,0 +1,99 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-1/materials.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/materials.xml new file mode 100644 index 0000000..a69951a --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-1/plots.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/plots.xml new file mode 100644 index 0000000..0d1b38c --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 2. + 50. 50. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-1/settings.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/settings.xml new file mode 100644 index 0000000..011acd2 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-2/generate_materials.py b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..aadfbed --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/generate_materials.py @@ -0,0 +1,38 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Tuballoy" +mat.set_density('sum') +mat.add_nuclide('U234', 2.6428e-06) +mat.add_nuclide('U235', 3.4597e-04) +mat.add_nuclide('U238', 4.7702e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Oralloy" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9157e-04) +mat.add_nuclide('U235', 4.4825e-02) +mat.add_nuclide('U238', 2.6391e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "2024 Aluminum" +mat.set_density('sum') +mat.add_element('Mg', 1.0295e-03) +mat.add_element('Al', 5.7868e-02) +mat.add_element('Mn', 1.5182e-04) +mat.add_element('Cu', 1.1550e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Stainless Steel" +mat.set_density('sum') +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-2/geometry.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/geometry.xml new file mode 100644 index 0000000..61ad881 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/geometry.xml @@ -0,0 +1,100 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-2/materials.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/materials.xml new file mode 100644 index 0000000..0341b12 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-2/plots.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/plots.xml new file mode 100644 index 0000000..0d1b38c --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 2. + 50. 50. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-2/settings.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/settings.xml new file mode 100644 index 0000000..011acd2 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-3/generate_materials.py b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..64f7be3 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/generate_materials.py @@ -0,0 +1,38 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Tuballoy" +mat.set_density('sum') +mat.add_nuclide('U234', 2.6418e-06) +mat.add_nuclide('U235', 3.4583e-04) +mat.add_nuclide('U238', 4.7684e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Oralloy" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9172e-04) +mat.add_nuclide('U235', 4.4849e-02) +mat.add_nuclide('U238', 2.6305e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "2024 Aluminum" +mat.set_density('sum') +mat.add_element('Mg', 1.0295e-03) +mat.add_element('Al', 5.7868e-02) +mat.add_element('Mn', 1.5182e-04) +mat.add_element('Cu', 1.1550e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Stainless Steel" +mat.set_density('sum') +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-3/geometry.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/geometry.xml new file mode 100644 index 0000000..d30b320 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/geometry.xml @@ -0,0 +1,129 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-3/materials.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/materials.xml new file mode 100644 index 0000000..abfd9c9 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-3/plots.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/plots.xml new file mode 100644 index 0000000..0d1b38c --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 2. + 50. 50. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-3/settings.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/settings.xml new file mode 100644 index 0000000..96d1d07 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-3/settings.xml @@ -0,0 +1,19 @@ + + + + + + + 3000 + 20 + 10000 + + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-4/generate_materials.py b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..cf823cf --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/generate_materials.py @@ -0,0 +1,38 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Tuballoy" +mat.set_density('sum') +mat.add_nuclide('U234', 2.6428e-06) +mat.add_nuclide('U235', 3.4597e-04) +mat.add_nuclide('U238', 4.7702e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Oralloy" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9175e-04) +mat.add_nuclide('U235', 4.4851e-02) +mat.add_nuclide('U238', 2.6306e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "2024 Aluminum" +mat.set_density('sum') +mat.add_element('Mg', 1.0295e-03) +mat.add_element('Al', 5.7868e-02) +mat.add_element('Mn', 1.5182e-04) +mat.add_element('Cu', 1.1550e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Stainless Steel" +mat.set_density('sum') +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-4/geometry.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/geometry.xml new file mode 100644 index 0000000..62f9699 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/geometry.xml @@ -0,0 +1,133 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-4/materials.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/materials.xml new file mode 100644 index 0000000..c6ba9b3 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/materials.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-4/plots.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/plots.xml new file mode 100644 index 0000000..0d1b38c --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 2. + 50. 50. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-001/openmc/case-4/settings.xml b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/settings.xml new file mode 100644 index 0000000..c96d3db --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-001/openmc/case-4/settings.xml @@ -0,0 +1,21 @@ + + + + + + + 3000 + 20 + 10000 + + + + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-002/mcdc/ieu-met-fast-002.py b/icsbep/openmc/ieu-met-fast-002/mcdc/ieu-met-fast-002.py new file mode 100644 index 0000000..b347a71 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-002/mcdc/ieu-met-fast-002.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.007777699999999999], + ['U238',0.039671]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034603], + ['U238',0.047711]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=7.62, bc='interface') +s3 = mcdc.surface('plane-z', z=39.571, bc='interface') +s4 = mcdc.surface('plane-z', z=47.0894, bc='vacuum') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=19.05, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.6446, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s6, fill=m2) +c2 = mcdc.cell(+s2 & -s3 & -s5, fill=m1) +c3 = mcdc.cell(+s2 & -s3 & +s5 & -s6, fill=m2) +c4 = mcdc.cell(+s3 & -s4 & -s6, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-10.0,10.0], y=[-10.0,10.0], z=[0.0,47.0894], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-002/openmc/geometry.xml b/icsbep/openmc/ieu-met-fast-002/openmc/geometry.xml new file mode 100644 index 0000000..8f2d33b --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-002/openmc/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-002/openmc/materials.xml b/icsbep/openmc/ieu-met-fast-002/openmc/materials.xml new file mode 100644 index 0000000..98e4bd5 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-002/openmc/materials.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-002/openmc/settings.xml b/icsbep/openmc/ieu-met-fast-002/openmc/settings.xml new file mode 100644 index 0000000..c79af1f --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-002/openmc/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -10.0 -10.0 0.0 + 10.0 10.0 47.0894 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-003/mcdc/ieu-met-fast-003_case-2.py b/icsbep/openmc/ieu-met-fast-003/mcdc/ieu-met-fast-003_case-2.py new file mode 100644 index 0000000..afb88e4 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-003/mcdc/ieu-met-fast-003_case-2.py @@ -0,0 +1,59 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 36 wt% U-235 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.017118], + ['U238',0.029211], + ['C0',0.0007738900000000001], + ['Fe54',7.047901000000001e-06], + ['Fe56',0.00011063697320000001], + ['Fe57',2.5550902e-06], + ['Fe58',3.400356e-07], + ['W180',1.2104399999999999e-08], + ['W182',2.673055e-06], + ['W183',1.4434497e-06], + ['W184',3.0906568000000003e-06], + ['W186',2.8677341e-06], + ['Cu63',0.000263689695], + ['Cu65',0.00011764030499999999], + ['Ni58',0.00028107590471999997], + ['Ni60',0.00010826993527999999], + ['Ni61',4.70641912e-06], + ['Ni62',1.5006123600000001e-05], + ['Ni64',3.82161728e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.324, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-003/openmc/case-2/generate_materials.py b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..e28f2b6 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/generate_materials.py @@ -0,0 +1,18 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "36 wt% U-235" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5272e-04) +mat.add_nuclide('U235', 1.7118e-02) +mat.add_nuclide('U238', 2.9211e-02) +mat.add_element('C', 7.7389e-04) +mat.add_element('Fe', 1.2058e-04) +mat.add_element('W', 1.0087e-05) +mat.add_element('Cu', 3.8133e-04) +mat.add_element('Ni', 4.1288e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-003/openmc/case-2/geometry.xml b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/geometry.xml new file mode 100644 index 0000000..621cdfb --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/geometry.xml @@ -0,0 +1,15 @@ + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-003/openmc/case-2/materials.xml b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/materials.xml new file mode 100644 index 0000000..c4ed53d --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/materials.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-003/openmc/case-2/settings.xml b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-003/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-004/mcdc/ieu-met-fast-004_case-2.py b/icsbep/openmc/ieu-met-fast-004/mcdc/ieu-met-fast-004_case-2.py new file mode 100644 index 0000000..7cde1c1 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-004/mcdc/ieu-met-fast-004_case-2.py @@ -0,0 +1,60 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 36 wt% U-235 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.017384], + ['U238',0.029662], + ['C0',0.00065752], + ['Fe54',7.071281e-06], + ['Fe56',0.0001110039892], + ['Fe57',2.5635662e-06], + ['Fe58',3.411636e-07], + ['W180',1.2145200000000001e-08], + ['W182',2.6820650000000002e-06], + ['W183',1.4483151000000001e-06], + ['W184',3.1010744e-06], + ['W186',2.8774003e-06]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.077716]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=2.788, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.0, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.2, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-004/openmc/case-2/generate_materials.py b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..fad1822 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "36 wt% U-235" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5652e-04) +mat.add_nuclide('U235', 1.7384e-02) +mat.add_nuclide('U238', 2.9662e-02) +mat.add_element('C', 6.5752e-04) +mat.add_element('Fe', 1.2098e-04) +mat.add_element('W', 1.0121e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 7.7716e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-004/openmc/case-2/geometry.xml b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/geometry.xml new file mode 100644 index 0000000..3e78d5d --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-004/openmc/case-2/materials.xml b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/materials.xml new file mode 100644 index 0000000..8067d93 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/materials.xml @@ -0,0 +1,24 @@ + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-004/openmc/case-2/settings.xml b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-004/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-005/mcdc/ieu-met-fast-005_case-2.py b/icsbep/openmc/ieu-met-fast-005/mcdc/ieu-met-fast-005_case-2.py new file mode 100644 index 0000000..fafa743 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-005/mcdc/ieu-met-fast-005_case-2.py @@ -0,0 +1,109 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 36 wt% U-235 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.017154], + ['U238',0.029297], + ['W180',1.2853199999999999e-08], + ['W182',2.838415e-06], + ['W183',1.5327441e-06], + ['W184',3.2818504e-06], + ['W186',3.0451372999999996e-06], + ['Fe54',7.203377999999999e-06], + ['Fe56',0.00011307762959999999], + ['Fe57',2.6114555999999998e-06], + ['Fe58',3.475368e-07], + ['C0',0.00064945], + ['Cu63',0.000185259765], + ['Cu65',8.2650235e-05], + ['Ni58',0.00019747747151999999], + ['Ni60',7.606796848e-05], + ['Ni61',3.30662192e-06], + ['Ni62',1.0542957600000001e-05], + ['Ni64',2.68498048e-06]]) +# Material Name: Steel reflector #1 +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00463420825], + ['Fe56',0.0727471589], + ['Fe57',0.00168004915], + ['Fe58',0.00022358369999999999], + ['C0',0.0011251], + ['Si28',0.000147917960784], + ['Si29',7.510852008000001e-06], + ['Si30',4.951187208e-06], + ['Cr50',1.12922205e-05], + ['Cr52',0.00021775923209999999], + ['Cr53',2.4692148899999996e-05], + ['Cr54',6.146398499999999e-06], + ['Mn55',0.00032796], + ['Ni58',0.00015674706225], + ['Ni60',6.037868775e-05], + ['Ni61',2.6246197500000005e-06], + ['Ni62',8.36843625e-06], + ['Ni64',2.1311940000000003e-06], + ['Cu63',0.000147047475], + ['Cu65',6.5602525e-05]]) +# Material Name: Steel reflector #2 +m3 = mcdc.material(nuclides=[ + ['Fe54',0.004698678600000001], + ['Fe56',0.07375920552000001], + ['Fe57',0.0017034217200000003], + ['Fe58',0.00022669416], + ['C0',0.0011407], + ['Si28',0.000149974682648], + ['Si29',7.615286475999999e-06], + ['Si30',5.020030875999999e-06], + ['Cr50',1.14495095e-05], + ['Cr52',0.00022079239389999998], + ['Cr53',2.50360851e-05], + ['Cr54',6.232011500000001e-06], + ['Mn55',0.00033253], + ['Ni58',0.00015892552305], + ['Ni60',6.121782695e-05], + ['Ni61',2.66109655e-06], + ['Ni62',8.48474025e-06], + ['Ni64',2.1608132e-06], + ['Cu63',0.000149094315], + ['Cu65',6.6515685e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=2.686, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.25, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.0, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=21.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-005/openmc/case-2/generate_materials.py b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..cacfba3 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/generate_materials.py @@ -0,0 +1,42 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "36 wt% U-235" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5511e-04) +mat.add_nuclide('U235', 1.7154e-02) +mat.add_nuclide('U238', 2.9297e-02) +mat.add_element('W', 1.0711e-05) +mat.add_element('Fe', 1.2324e-04) +mat.add_element('C', 6.4945e-04) +mat.add_element('Cu', 2.6791e-04) +mat.add_element('Ni', 2.9008e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Steel reflector #1" +mat.set_density('sum') +mat.add_element('Fe', 7.9285e-02) +mat.add_element('C', 1.1251e-03) +mat.add_element('Si', 1.6038e-04) +mat.add_element('Cr', 2.5989e-04) +mat.add_element('Mn', 3.2796e-04) +mat.add_element('Ni', 2.3025e-04) +mat.add_element('Cu', 2.1265e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel reflector #2" +mat.set_density('sum') +mat.add_element('Fe', 8.0388e-02) +mat.add_element('C', 1.1407e-03) +mat.add_element('Si', 1.6261e-04) +mat.add_element('Cr', 2.6351e-04) +mat.add_element('Mn', 3.3253e-04) +mat.add_element('Ni', 2.3345e-04) +mat.add_element('Cu', 2.1561e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-005/openmc/case-2/geometry.xml b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/geometry.xml new file mode 100644 index 0000000..66181c7 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-005/openmc/case-2/materials.xml b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/materials.xml new file mode 100644 index 0000000..3ebf417 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/materials.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-005/openmc/case-2/settings.xml b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-005/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-006/mcdc/ieu-met-fast-006_case-2.py b/icsbep/openmc/ieu-met-fast-006/mcdc/ieu-met-fast-006_case-2.py new file mode 100644 index 0000000..3b39078 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-006/mcdc/ieu-met-fast-006_case-2.py @@ -0,0 +1,83 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 36 wt% U-235 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.017161], + ['U238',0.02931], + ['W180',1.28652e-08], + ['W182',2.841065e-06], + ['W183',1.5341751000000002e-06], + ['W184',3.2849144e-06], + ['W186',3.0479802999999996e-06], + ['Fe54',7.2156524999999994e-06], + ['Fe56',0.00011327031299999999], + ['Fe57',2.6159055e-06], + ['Fe58',3.48129e-07], + ['C0',0.00064888], + ['Cu63',0.00018501082500000003], + ['Cu65',8.253917500000001e-05], + ['Ni58',0.00019721197160999998], + ['Ni60',7.596569839e-05], + ['Ni61',3.3021763099999997e-06], + ['Ni62',1.0528783050000001e-05], + ['Ni64',2.68137064e-06]]) +# Material Name: Duralumin reflector #1 +m2 = mcdc.material(nuclides=[ + ['Al27',0.052342], + ['Fe54',5.5988085999999995e-05], + ['Fe56',0.0008788932152], + ['Fe57',2.02974772e-05], + ['Fe58',2.7012216e-06], + ['Cu63',0.00068191581], + ['Cu65',0.00030422418999999997]]) +# Material Name: Duralumin reflector #2 +m3 = mcdc.material(nuclides=[ + ['Al27',0.052067], + ['Fe54',5.5694667e-05], + ['Fe56',0.0008742871644000001], + ['Fe57',2.0191103400000002e-05], + ['Fe58',2.6870652e-06], + ['Cu63',0.0006783407550000001], + ['Cu65',0.000302629245]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=2.1, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.25, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.0, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=25.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-006/openmc/case-2/generate_materials.py b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..a3d057b --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/generate_materials.py @@ -0,0 +1,34 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "36 wt% U-235" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5518e-04) +mat.add_nuclide('U235', 1.7161e-02) +mat.add_nuclide('U238', 2.9310e-02) +mat.add_element('W', 1.0721e-05) +mat.add_element('Fe', 1.2345e-04) +mat.add_element('C', 6.4888e-04) +mat.add_element('Cu', 2.6755e-04) +mat.add_element('Ni', 2.8969e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Duralumin reflector #1" +mat.set_density('sum') +mat.add_element('Al', 5.2342e-02) +mat.add_element('Fe', 9.5788e-04) +mat.add_element('Cu', 9.8614e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Duralumin reflector #2" +mat.set_density('sum') +mat.add_element('Al', 5.2067e-02) +mat.add_element('Fe', 9.5286e-04) +mat.add_element('Cu', 9.8097e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-006/openmc/case-2/geometry.xml b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/geometry.xml new file mode 100644 index 0000000..d25c5c4 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-006/openmc/case-2/materials.xml b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/materials.xml new file mode 100644 index 0000000..a70a276 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/materials.xml @@ -0,0 +1,46 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-006/openmc/case-2/settings.xml b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-006/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-007/mcdc/ieu-met-fast-007_case-4.py b/icsbep/openmc/ieu-met-fast-007/mcdc/ieu-met-fast-007_case-4.py new file mode 100644 index 0000000..f0a0cba --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-007/mcdc/ieu-met-fast-007_case-4.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U235',0.0049831], + ['U238',0.043108]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.0048461], + ['U238',0.042695]]) +m3 = mcdc.material(nuclides=[ + ['U235',0.00034701], + ['U238',0.047846]]) +m4 = mcdc.material(nuclides=[ + ['U235',0.00010058], + ['U238',0.047677]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.25014, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.10996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=7.62, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=12.54604, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.67, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=41.91, bc='vacuum') +s7 = mcdc.surface('plane-z', z=-57.4675, bc='vacuum') +s8 = mcdc.surface('plane-z', z=-41.73361, bc='interface') +s9 = mcdc.surface('plane-z', z=-38.24644, bc='interface') +s10 = mcdc.surface('plane-z', z=-22.3901, bc='interface') +s11 = mcdc.surface('plane-z', z=4.35102, bc='interface') +s12 = mcdc.surface('plane-z', z=17.16665, bc='interface') +s13 = mcdc.surface('plane-z', z=23.8125, bc='interface') +s14 = mcdc.surface('plane-z', z=39.0525, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s3 & +s8 & -s10, fill=m2) +c2 = mcdc.cell(-s4 & +s10 & -s11, fill=m2) +c3 = mcdc.cell(-s2 & +s11 & -s13, fill=m2) +c4 = mcdc.cell(-s1 & +s13 & -s14, fill=m2) +c5 = mcdc.cell(+s3 & -s5 & +s8 & -s9, fill=m3) +c6 = mcdc.cell(+s3 & -s5 & +s9 & -s10, fill=m1) +c7 = mcdc.cell(+s4 & -s5 & +s10 & -s11, fill=m1) +c8 = mcdc.cell(+s2 & -s5 & +s11 & -s12, fill=m1) +c9 = mcdc.cell(+s2 & -s5 & +s12 & -s13, fill=m3) +c10 = mcdc.cell(+s5 & -s6 & +s7 & -s14, fill=m4) +c11 = mcdc.cell(-s5 & +s7 & -s8, fill=m4) +c12 = mcdc.cell(+s1 & -s5 & +s13 & -s14, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-007/openmc/case-4/geometry.xml b/icsbep/openmc/ieu-met-fast-007/openmc/case-4/geometry.xml new file mode 100644 index 0000000..9e048b6 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-007/openmc/case-4/geometry.xml @@ -0,0 +1,41 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-007/openmc/case-4/materials.xml b/icsbep/openmc/ieu-met-fast-007/openmc/case-4/materials.xml new file mode 100644 index 0000000..bf55bf5 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-007/openmc/case-4/materials.xml @@ -0,0 +1,46 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-007/openmc/case-4/settings.xml b/icsbep/openmc/ieu-met-fast-007/openmc/case-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-007/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-009/mcdc/ieu-met-fast-009.py b/icsbep/openmc/ieu-met-fast-009/mcdc/ieu-met-fast-009.py new file mode 100644 index 0000000..b3640e3 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-009/mcdc/ieu-met-fast-009.py @@ -0,0 +1,136 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 36 wt% U-235, Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.01744], + ['U238',0.02999], + ['C0',0.00047009], + ['Fe54',9.454872e-06], + ['Fe56',0.0001484212704], + ['Fe57',3.4276943999999994e-06], + ['Fe58',4.561632e-07], + ['W180',1.4740799999999999e-08], + ['W182',3.25526e-06], + ['W183',1.7578404000000002e-06], + ['W184',3.7638175999999998e-06], + ['W186',3.4923412e-06]]) +# Material Name: 36 wt% U-235, Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.017415], + ['U238',0.029887], + ['C0',0.00037502], + ['Fe54',9.428569500000001e-06], + ['Fe56',0.00014800837740000001], + ['Fe57',3.4181589000000006e-06], + ['Fe58',4.548942e-07], + ['W180',1.4699999999999998e-08], + ['W182',3.24625e-06], + ['W183',1.752975e-06], + ['W184',3.7534e-06], + ['W186',3.4826749999999992e-06]]) +# Material Name: 36 wt% U-235, Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.017418], + ['U238',0.029651], + ['C0',0.00055986], + ['Fe54',9.383563e-06], + ['Fe56',0.0001473018716], + ['Fe57',3.4018426e-06], + ['Fe58',4.527228e-07], + ['W180',1.4630399999999996e-08], + ['W182',3.2308799999999997e-06], + ['W183',1.7446752e-06], + ['W184',3.7356287999999997e-06], + ['W186',3.4661856000000002e-06]]) +# Material Name: 36 wt% U-235, Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.017356], + ['U238',0.029786], + ['C0',0.00074727], + ['Fe54',7.045562999999999e-06], + ['Fe56',0.0001106002716], + ['Fe57',2.5542426e-06], + ['Fe58',3.399228e-07], + ['W180',1.4645999999999998e-08], + ['W182',3.234325e-06], + ['W183',1.7465355000000002e-06], + ['W184',3.7396119999999996e-06], + ['W186',3.4698815000000002e-06]]) +# Material Name: 36 wt% U-235, Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',0.017417], + ['U238',0.029662999999999995], + ['C0',0.00055983], + ['Fe54',5.864873000000001e-06], + ['Fe56',9.206596360000001e-05], + ['Fe57',2.1262046000000002e-06], + ['Fe58',2.8295880000000003e-07], + ['W180',7.31472e-09], + ['W182',1.6153340000000003e-06], + ['W183',8.7228036e-07], + ['W184',1.86769184e-06], + ['W186',1.7329790799999999e-06]]) +# Material Name: Polyethylene, Layer 1 +# S(a,b): c_H_in_CH2 (Not Implemented) +m6 = mcdc.material(nuclides=[ + ['H1',0.075542], + ['C0',0.037771]]) +# Material Name: Polyethylene, Layer 2 +# S(a,b): c_H_in_CH2 (Not Implemented) +m7 = mcdc.material(nuclides=[ + ['H1',0.07417], + ['C0',0.037085]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.445, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.25, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.15, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=18.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-009/openmc/generate_materials.py b/icsbep/openmc/ieu-met-fast-009/openmc/generate_materials.py new file mode 100644 index 0000000..856d9d2 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-009/openmc/generate_materials.py @@ -0,0 +1,76 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "36 wt% U-235, Layer 1" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5922e-04) +mat.add_nuclide('U235', 1.7440e-02) +mat.add_nuclide('U238', 2.9990e-02) +mat.add_element('C', 4.7009e-04) +mat.add_element('Fe', 1.6176e-04) +mat.add_element('W', 1.2284e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "36 wt% U-235, Layer 2" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5878e-04) +mat.add_nuclide('U235', 1.7415e-02) +mat.add_nuclide('U238', 2.9887e-02) +mat.add_element('C', 3.7502e-04) +mat.add_element('Fe', 1.6131e-04) +mat.add_element('W', 1.2250e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "36 wt% U-235, Layer 3" +mat.set_density('sum') +mat.add_nuclide('U234', 1.5803e-04) +mat.add_nuclide('U235', 1.7418e-02) +mat.add_nuclide('U238', 2.9651e-02) +mat.add_element('C', 5.5986e-04) +mat.add_element('Fe', 1.6054e-04) +mat.add_element('W', 1.2192e-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "36 wt% U-235, Layer 4" +mat.set_density('sum') +mat.add_nuclide('U234', 1.3423e-04) +mat.add_nuclide('U235', 1.7356e-02) +mat.add_nuclide('U238', 2.9786e-02) +mat.add_element('C', 7.4727e-04) +mat.add_element('Fe', 1.2054e-04) +mat.add_element('W', 1.2205e-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "36 wt% U-235, Layer 5" +mat.set_density('sum') +mat.add_nuclide('U234', 1.6281e-04) +mat.add_nuclide('U235', 1.7417e-02) +mat.add_nuclide('U238', 2.9663e-02) +mat.add_element('C', 5.5983e-04) +mat.add_element('Fe', 1.0034e-04) +mat.add_element('W', 6.0956e-06) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Polyethylene, Layer 1" +mat.set_density('sum') +mat.add_nuclide('H1', 7.5542e-02) +mat.add_element('C', 3.7771e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Polyethylene, Layer 2" +mat.set_density('sum') +mat.add_nuclide('H1', 7.4170e-02) +mat.add_element('C', 3.7085e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-009/openmc/geometry.xml b/icsbep/openmc/ieu-met-fast-009/openmc/geometry.xml new file mode 100644 index 0000000..ed22bf3 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-009/openmc/geometry.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-009/openmc/materials.xml b/icsbep/openmc/ieu-met-fast-009/openmc/materials.xml new file mode 100644 index 0000000..8df6989 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-009/openmc/materials.xml @@ -0,0 +1,95 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-009/openmc/settings.xml b/icsbep/openmc/ieu-met-fast-009/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-009/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/ieu-met-fast-010/mcdc/ieu-met-fast-010.py b/icsbep/openmc/ieu-met-fast-010/mcdc/ieu-met-fast-010.py new file mode 100644 index 0000000..546a78e --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-010/mcdc/ieu-met-fast-010.py @@ -0,0 +1,380 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Empty matrix above and below reflector +m1 = mcdc.material(nuclides=[ + ['Cr50',5.166596050000001e-05], + ['Cr52',0.0009963266201], + ['Cr53',0.00011297544090000002], + ['Cr54',2.8121978500000004e-05], + ['Ni58',0.000326888254575], + ['Ni60',0.000125916770425], + ['Ni61',5.473514825e-06], + ['Ni62',1.7451960375e-05], + ['Ni64',4.4444998000000005e-06], + ['Fe54',0.000250115733], + ['Fe56',0.0039262821156], + ['Fe57',9.06749766e-05], + ['Fe58',1.2067174799999999e-05], + ['C0',1.87415e-05], + ['Mo100',8.045162832e-07], + ['Mo92',1.2094990797e-06], + ['Mo94',7.585274110999998e-07], + ['Mo95',1.3105590069000002e-06], + ['Mo96',1.3766112468999998e-06], + ['Mo97',7.911407046e-07], + ['Mo98',2.0056762676e-06], + ['Mn55',0.000105905], + ['Cu63',1.1915858850000001e-05], + ['Cu65',5.31604115e-06], + ['Si28',6.30025555564e-05], + ['Si29',3.1990900118e-06], + ['Si30',2.1088544318e-06]]) +# Material Name: Empty matrix surrounding radial reflector +m2 = mcdc.material(nuclides=[ + ['Cr50',5.12523165e-05], + ['Cr52',0.0009883499073], + ['Cr53',0.0001120709457], + ['Cr54',2.7896830499999997e-05], + ['Ni58',0.000324270017001], + ['Ni60',0.000124908229999], + ['Ni61',5.429674270999999e-06], + ['Ni62',1.7312177505e-05], + ['Ni64',4.4089012240000005e-06], + ['Fe54',0.00024811323600000003], + ['Fe56',0.003894847195200001], + ['Fe57',8.994900720000001e-05], + ['Fe58',1.19705616e-05], + ['C0',1.85933e-05], + ['Mo100',7.981076543999999e-07], + ['Mo92',1.1998644324000002e-06], + ['Mo94',7.524851211999999e-07], + ['Mo95',1.3001193348e-06], + ['Mo96',1.3656454147999998e-06], + ['Mo97',7.848386232000001e-07], + ['Mo98',1.9896994192e-06], + ['Mn55',0.000105057], + ['Cu63',1.18207776e-05], + ['Cu65',5.2736224e-06], + ['Si28',6.24975980584e-05], + ['Si29',3.1734497107999994e-06], + ['Si30',2.0919522308e-06]]) +# Material Name: DU radial reflector +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',8.56868e-05], + ['U238',0.0383747], + ['Cr50',7.3648619e-05], + ['Cr52',0.0014202403078], + ['Cr53',0.00016104385019999998], + ['Cr54',4.0087223e-05], + ['Ni58',0.00046721312623799994], + ['Ni60',0.00017996965976199998], + ['Ni61',7.823156497999999e-06], + ['Ni62',2.494364619e-05], + ['Ni64',6.352411312e-06], + ['Fe54',0.00035844111800000005], + ['Fe56',0.005626758997600001], + ['Fe57',0.0001299464036], + ['Fe58',1.72934808e-05], + ['C0',3.77935e-05], + ['Mo100',1.049146224e-06], + ['Mo92',1.5772724790000004e-06], + ['Mo94',9.89173477e-07], + ['Mo95',1.7090617830000003e-06], + ['Mo96',1.7951985830000002e-06], + ['Mo97',1.031703522e-06], + ['Mo98',2.6155439320000003e-06], + ['Mn55',0.000146803], + ['Cu63',1.4993103e-05], + ['Cu65',6.688897e-06], + ['H1',2.5376347272078e-06], + ['H2',3.952727922e-10], + ['Si28',7.098697118368e-05], + ['Si29',3.60451585616e-06], + ['Si30',2.37611296016e-06], + ['Cl35',3.32951004738e-06], + ['Cl37',1.0650299526200002e-06], + ['F19',1.30132e-05]]) +# Material Name: Lower DU axial reflector +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',8.24312e-05], + ['U238',0.0369113], + ['Cr50',7.50064315e-05], + ['Cr52',0.0014464243703], + ['Cr53',0.0001640129127], + ['Cr54',4.08262855e-05], + ['Ni58',0.0004791497298839999], + ['Ni60',0.000184567618116], + ['Ni61',8.023026564e-06], + ['Ni62',2.5580919420000006e-05], + ['Ni64',6.514706016e-06], + ['Fe54',0.0003662517915], + ['Fe56',0.0057493698678], + ['Fe57',0.0001327780233], + ['Fe58',1.7670317400000002e-05], + ['Al27',0.00041674699999999997], + ['C0',3.97675e-05], + ['Mo100',1.093335264e-06], + ['Mo92',1.6437056940000001e-06], + ['Mo94',1.030836522e-06], + ['Mo95',1.7810458380000002e-06], + ['Mo96',1.8708106379999998e-06], + ['Mo97',1.075157892e-06], + ['Mo98',2.725708152e-06], + ['Mn55',0.000146859], + ['Cu63',1.476608355e-05], + ['Cu65',6.5876164499999996e-06], + ['H1',2.8173311605002e-06], + ['H2',4.3883949980000003e-10], + ['Si28',7.666472251416e-05], + ['Si29',3.89281586892e-06], + ['Si30',2.56616161692e-06], + ['Cl35',3.69063491346e-06], + ['Cl37',1.18054508654e-06], + ['F19',1.44249e-05]]) +# Material Name: Upper DU axial reflector +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',8.31425e-05], + ['U238',0.0372293], + ['Cr50',7.50064315e-05], + ['Cr52',0.0014464243703], + ['Cr53',0.0001640129127], + ['Cr54',4.08262855e-05], + ['Ni58',0.000479149729884], + ['Ni60',0.000184567618116], + ['Ni61',8.023026564e-06], + ['Ni62',2.5580919420000002e-05], + ['Ni64',6.514706016e-06], + ['Fe54',0.0003662804320000001], + ['Fe56',0.0057498194624], + ['Fe57',0.0001327884064], + ['Fe58',1.76716992e-05], + ['Al27',0.000416747], + ['C0',3.99149e-05], + ['Mo100',1.093335264e-06], + ['Mo92',1.643705694e-06], + ['Mo94',1.030836522e-06], + ['Mo95',1.7810458380000002e-06], + ['Mo96',1.870810638e-06], + ['Mo97',1.075157892e-06], + ['Mo98',2.725708152e-06], + ['Mn55',0.000146859], + ['Cu63',1.476608355e-05], + ['Cu65',6.5876164499999996e-06], + ['H1',2.8538254759902e-06], + ['H2',4.4452400979999994e-10], + ['Si28',7.666472251416e-05], + ['Si29',3.89281586892e-06], + ['Si30',2.56616161692e-06], + ['Cl35',3.7381848391799994e-06], + ['Cl37',1.19575516082e-06], + ['F19',1.46107e-05]]) +# Material Name: Core 1 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',0.0034854300000000003], + ['U238',0.0352634], + ['Cr50',8.08461115e-05], + ['Cr52',0.0015590367863], + ['Cr53',0.0001767822567], + ['Cr54',4.4004845500000004e-05], + ['Ni58',0.000509932061757], + ['Ni60',0.00019642491724299998], + ['Ni61',8.538455147e-06], + ['Ni62',2.7224331285e-05], + ['Ni64',6.933234568e-06], + ['Fe54',0.00038909463599999994], + ['Fe56',0.0061079536751999985], + ['Fe57',0.0001410592872], + ['Fe58',1.87724016e-05], + ['C0',9.6299e-05], + ['Mo100',1.152978288e-06], + ['Mo92',1.733372223e-06], + ['Mo94',1.087070149e-06], + ['Mo95',1.878204471e-06], + ['Mo96',1.9728660709999996e-06], + ['Mo97',1.133809314e-06], + ['Mo98',2.8743994839999998e-06], + ['Mn55',0.000163509], + ['Cu63',1.651530195e-05], + ['Cu65',7.36799805e-06], + ['H1',1.945496961108e-05], + ['H2',3.0303889199999992e-09], + ['Si28',6.603654310968001e-05], + ['Si29',3.35314724316e-06], + ['Si30',2.21040964716e-06], + ['Cl35',2.5267982038199997e-05], + ['Cl37',8.0826179618e-06], + ['F19',9.9122e-05]]) +# Material Name: Core 2 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',0.0034766599999999995], + ['U238',0.0353869], + ['Cr50',8.143312100000001e-05], + ['Cr52',0.0015703566802], + ['Cr53',0.0001780658418], + ['Cr54',4.4324357e-05], + ['Ni58',0.000513745048926], + ['Ni60',0.000197893673074], + ['Ni61',8.602300946e-06], + ['Ni62',2.7427899630000002e-05], + ['Ni64',6.985077424000001e-06], + ['Fe54',0.00039205454399999996], + ['Fe56',0.006154417900799999], + ['Fe57',0.0001421323488], + ['Fe58',1.89152064e-05], + ['C0',9.64166e-05], + ['Mo100',1.167321456e-06], + ['Mo92',1.7549355510000002e-06], + ['Mo94',1.100593413e-06], + ['Mo95',1.9015695270000002e-06], + ['Mo96',1.9974087269999997e-06], + ['Mo97',1.147914018e-06], + ['Mo98',2.910157308e-06], + ['Mn55',0.000164823], + ['Cu63',1.675705035e-05], + ['Cu65',7.475849650000001e-06], + ['H1',1.9446770888148e-05], + ['H2',3.029111852e-09], + ['Si28',6.843792728784e-05], + ['Si29',3.47508268008e-06], + ['Si30',2.2907900320799997e-06], + ['Cl35',2.5357384384199998e-05], + ['Cl37',8.1112156158e-06], + ['F19',9.947259999999999e-05]]) +# Material Name: Core 3 +# Depletable +m8 = mcdc.material(nuclides=[ + ['U235',0.0034854300000000003], + ['U238',0.0352634], + ['Cr50',8.08461115e-05], + ['Cr52',0.0015590367863], + ['Cr53',0.0001767822567], + ['Cr54',4.4004845500000004e-05], + ['Ni58',0.000509932061757], + ['Ni60',0.00019642491724299998], + ['Ni61',8.538455147e-06], + ['Ni62',2.7224331285000004e-05], + ['Ni64',6.933234568e-06], + ['Fe54',0.000389094636], + ['Fe56',0.006107953675199999], + ['Fe57',0.0001410592872], + ['Fe58',1.87724016e-05], + ['C0',9.62606e-05], + ['Mo100',1.152978288e-06], + ['Mo92',1.733372223e-06], + ['Mo94',1.087070149e-06], + ['Mo95',1.8782044709999999e-06], + ['Mo96',1.9728660709999996e-06], + ['Mo97',1.133809314e-06], + ['Mo98',2.8743994839999998e-06], + ['Mn55',0.000163509], + ['Cu63',1.651530195e-05], + ['Cu65',7.36799805e-06], + ['H1',1.9444071308646e-05], + ['H2',3.0286913539999996e-09], + ['Si28',6.603654310968001e-05], + ['Si29',3.35314724316e-06], + ['Si30',2.21040964716e-06], + ['Cl35',2.5253435215799997e-05], + ['Cl37',8.0779647842e-06], + ['F19',9.9065e-05]]) +# Material Name: Core 4 +# Depletable +m9 = mcdc.material(nuclides=[ + ['U235',0.00347666], + ['U238',0.0353869], + ['Cr50',8.143312100000001e-05], + ['Cr52',0.0015703566802], + ['Cr53',0.0001780658418], + ['Cr54',4.4324357e-05], + ['Ni58',0.000513745048926], + ['Ni60',0.000197893673074], + ['Ni61',8.602300946e-06], + ['Ni62',2.7427899630000002e-05], + ['Ni64',6.9850774240000005e-06], + ['Fe54',0.000392054544], + ['Fe56',0.0061544179008], + ['Fe57',0.0001421323488], + ['Fe58',1.89152064e-05], + ['C0',9.637809999999998e-05], + ['Mo100',1.167321456e-06], + ['Mo92',1.7549355510000004e-06], + ['Mo94',1.100593413e-06], + ['Mo95',1.9015695270000002e-06], + ['Mo96',1.9974087269999997e-06], + ['Mo97',1.147914018e-06], + ['Mo98',2.910157308e-06], + ['Mn55',0.000164823], + ['Cu63',1.675705035e-05], + ['Cu65',7.475849650000001e-06], + ['H1',1.9435772601288003e-05], + ['H2',3.027398712e-09], + ['Si28',6.843792728784e-05], + ['Si29',3.47508268008e-06], + ['Si30',2.2907900320799997e-06], + ['Cl35',2.5342761797099997e-05], + ['Cl37',8.1065382029e-06], + ['F19',9.94154e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=40.996, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=65.157, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=96.623, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-121.92, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-120.975, bc='interface') +s6 = mcdc.surface('plane-z', z=-120.461, bc='interface') +s7 = mcdc.surface('plane-z', z=-38.181, bc='interface') +s8 = mcdc.surface('plane-z', z=-22.941, bc='interface') +s9 = mcdc.surface('plane-z', z=0.0, bc='interface') +s10 = mcdc.surface('plane-z', z=22.941, bc='interface') +s11 = mcdc.surface('plane-z', z=38.181, bc='interface') +s12 = mcdc.surface('plane-z', z=120.461, bc='interface') +s13 = mcdc.surface('plane-z', z=120.975, bc='interface') +s14 = mcdc.surface('plane-z', z=121.92, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & +s4 & -s6, fill=m1) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s5, fill=m1) +c3 = mcdc.cell(-s1 & +s12 & -s14, fill=m1) +c4 = mcdc.cell(+s1 & -s2 & +s13 & -s14, fill=m1) +c5 = mcdc.cell(+s2 & -s3 & +s4 & -s14, fill=m2) +c6 = mcdc.cell(+s1 & -s2 & +s5 & -s13, fill=m3) +c7 = mcdc.cell(-s1 & +s6 & -s7, fill=m4) +c8 = mcdc.cell(-s1 & +s11 & -s12, fill=m5) +c9 = mcdc.cell(-s1 & +s9 & -s10, fill=m6) +c10 = mcdc.cell(-s1 & +s10 & -s11, fill=m7) +c11 = mcdc.cell(-s1 & +s8 & -s9, fill=m8) +c12 = mcdc.cell(-s1 & +s7 & -s8, fill=m9) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-97.0,97.0], y=[-97.0,97.0], z=[-122.0,122.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/ieu-met-fast-010/openmc/generate_materials.py b/icsbep/openmc/ieu-met-fast-010/openmc/generate_materials.py new file mode 100644 index 0000000..beca3f5 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-010/openmc/generate_materials.py @@ -0,0 +1,167 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Empty matrix above and below reflector" +mat.set_density('sum') +mat.add_element('Cr', 1.18909e-3) +mat.add_element('Ni', 4.80175e-4) +mat.add_element('Fe', 4.27914e-3) +mat.add_element('C', 1.87415e-5) +mat.add_element('Mo', 8.25653e-6) +mat.add_element('Mn', 1.05905e-4) +mat.add_element('Cu', 1.72319e-5) +mat.add_element('Si', 6.83105e-5) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Empty matrix surrounding radial reflector" +mat.set_density('sum') +mat.add_element('Cr', 1.17957e-3) +mat.add_element('Ni', 4.76329e-4) +mat.add_element('Fe', 4.24488e-3) +mat.add_element('C', 1.85933e-5) +mat.add_element('Mo', 8.19076e-6) +mat.add_element('Mn', 1.05057e-4) +mat.add_element('Cu', 1.70944e-5) +mat.add_element('Si', 6.77630e-5) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "DU radial reflector" +mat.set_density('sum') +mat.add_nuclide('U235', 8.56868e-5) +mat.add_nuclide('U238', 3.83747e-2) +mat.add_element('Cr', 1.69502e-3) +mat.add_element('Ni', 6.86302e-4) +mat.add_element('Fe', 6.13244e-3) +mat.add_element('C', 3.77935e-5) +mat.add_element('Mo', 1.07671e-5) +mat.add_element('Mn', 1.46803e-4) +mat.add_element('Cu', 2.16820e-5) +mat.add_element('H', 2.53803e-6) +mat.add_element('Si', 7.69676e-5) +mat.add_element('Cl', 4.39454e-6) +mat.add_element('F', 1.30132e-5) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lower DU axial reflector" +mat.set_density('sum') +mat.add_nuclide('U235', 8.24312e-5) +mat.add_nuclide('U238', 3.69113e-2) +mat.add_element('Cr', 1.72627e-3) +mat.add_element('Ni', 7.03836e-4) +mat.add_element('Fe', 6.26607e-3) +mat.add_element('Al', 4.16747e-4) +mat.add_element('C', 3.97675e-5) +mat.add_element('Mo', 1.12206e-5) +mat.add_element('Mn', 1.46859e-4) +mat.add_element('Cu', 2.13537e-5) +mat.add_element('H', 2.81777e-6) +mat.add_element('Si', 8.31237e-5) +mat.add_element('Cl', 4.87118e-6) +mat.add_element('F', 1.44249e-5) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Upper DU axial reflector" +mat.set_density('sum') +mat.add_nuclide('U235', 8.31425e-5) +mat.add_nuclide('U238', 3.72293e-2) +mat.add_element('Cr', 1.72627e-3) +mat.add_element('Ni', 7.03836e-4) +mat.add_element('Fe', 6.26656e-3) +mat.add_element('Al', 4.16747e-4) +mat.add_element('C', 3.99149e-5) +mat.add_element('Mo', 1.12206e-5) +mat.add_element('Mn', 1.46859e-4) +mat.add_element('Cu', 2.13537e-5) +mat.add_element('H', 2.85427e-6) +mat.add_element('Si', 8.31237e-5) +mat.add_element('Cl', 4.93394e-6) +mat.add_element('F', 1.46107e-5) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Core 1" +mat.set_density('sum') +mat.add_nuclide('U235', 3.48543e-3) +mat.add_nuclide('U238', 3.52634e-2) +mat.add_nuclide('U234', 3.34211e-5) +mat.add_nuclide('U236', 1.60227e-5) +mat.add_element('Cr', 1.86067e-3) +mat.add_element('Ni', 7.49053e-4) +mat.add_element('Fe', 6.65688e-3) +mat.add_element('C', 9.62990e-5) +mat.add_element('Mo', 1.18327e-5) +mat.add_element('Mn', 1.63509e-4) +mat.add_element('Cu', 2.38833e-5) +mat.add_element('H', 1.94580e-5) +mat.add_element('Si', 7.16001e-5) +mat.add_element('Cl', 3.33506e-5) +mat.add_element('F', 9.91220e-5) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Core 2" +mat.set_density('sum') +mat.add_nuclide('U235', 3.47666e-3) +mat.add_nuclide('U238', 3.53869e-2) +mat.add_nuclide('U234', 3.33328e-5) +mat.add_nuclide('U236', 1.59801e-5) +mat.add_element('Cr', 1.87418e-3) +mat.add_element('Ni', 7.54654e-4) +mat.add_element('Fe', 6.70752e-3) +mat.add_element('C', 9.64166e-5) +mat.add_element('Mo', 1.19799e-5) +mat.add_element('Mn', 1.64823e-4) +mat.add_element('Cu', 2.42329e-5) +mat.add_element('H', 1.94498e-5) +mat.add_element('Si', 7.42038e-5) +mat.add_element('Cl', 3.34686e-5) +mat.add_element('F', 9.94726e-5) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Core 3" +mat.set_density('sum') +mat.add_nuclide('U235', 3.48543e-3) +mat.add_nuclide('U238', 3.52634e-2) +mat.add_nuclide('U234', 3.34211e-5) +mat.add_nuclide('U236', 1.60227e-5) +mat.add_element('Cr', 1.86067e-3) +mat.add_element('Ni', 7.49053e-4) +mat.add_element('Fe', 6.65688e-3) +mat.add_element('C', 9.62606e-5) +mat.add_element('Mo', 1.18327e-5) +mat.add_element('Mn', 1.63509e-4) +mat.add_element('Cu', 2.38833e-5) +mat.add_element('H', 1.94471e-5) +mat.add_element('Si', 7.16001e-5) +mat.add_element('Cl', 3.33314e-5) +mat.add_element('F', 9.90650e-5) +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "Core 4" +mat.set_density('sum') +mat.add_nuclide('U235', 3.47666e-3) +mat.add_nuclide('U238', 3.53869e-2) +mat.add_nuclide('U234', 3.33328e-5) +mat.add_nuclide('U236', 1.59801e-5) +mat.add_element('Cr', 1.87418e-3) +mat.add_element('Ni', 7.54654e-4) +mat.add_element('Fe', 6.70752e-3) +mat.add_element('C', 9.63781e-5) +mat.add_element('Mo', 1.19799e-5) +mat.add_element('Mn', 1.64823e-4) +mat.add_element('Cu', 2.42329e-5) +mat.add_element('H', 1.94388e-5) +mat.add_element('Si', 7.42038e-5) +mat.add_element('Cl', 3.34493e-5) +mat.add_element('F', 9.94154e-5) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/ieu-met-fast-010/openmc/geometry.xml b/icsbep/openmc/ieu-met-fast-010/openmc/geometry.xml new file mode 100644 index 0000000..9b2ede4 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-010/openmc/geometry.xml @@ -0,0 +1,62 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-010/openmc/materials.xml b/icsbep/openmc/ieu-met-fast-010/openmc/materials.xml new file mode 100644 index 0000000..32b977f --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-010/openmc/materials.xml @@ -0,0 +1,332 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/ieu-met-fast-010/openmc/settings.xml b/icsbep/openmc/ieu-met-fast-010/openmc/settings.xml new file mode 100644 index 0000000..0d09ae8 --- /dev/null +++ b/icsbep/openmc/ieu-met-fast-010/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -97. -97. -122. 97. 97. 122. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-1.py b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-1.py new file mode 100644 index 0000000..b7eeab4 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-1.py @@ -0,0 +1,81 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Water with 1511 PPM +# S(a,b): c_H_in_H2O (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['H1',0.066737], + ['O16',0.033369], + ['B10',1.6769e-05], + ['B11',6.7497e-05]]) +# Material Name: Fuel (2.459 w/o with B-10 for impurities) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00056868], + ['U238',0.022268], + ['O16',0.045682999999999994], + ['B10',2.6055e-07]]) +# Material Name: Aluminum 6061 Cladding for Fuel +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0004900646472], + ['Mg25',6.219614399999999e-05], + ['Mg26',6.84592088e-05], + ['Al27',0.053985], + ['Si28',0.00029725625863999996], + ['Si29',1.5093824679999998e-05], + ['Si30',9.949916679999998e-06], + ['Ti46',3.8991975e-06], + ['Ti47',3.516367199999999e-06], + ['Ti48',3.48422836e-05], + ['Ti49',2.5569283e-06], + ['Ti50',2.4482234e-06], + ['Cr50',2.5213600500000003e-06], + ['Cr52',4.862191881e-05], + ['Cr53',5.51333529e-06], + ['Cr54',1.3723858500000001e-06], + ['Mn55',4.1191e-05], + ['Fe54',1.1052895e-05], + ['Fe56',0.000173506814], + ['Fe57',4.007029e-06], + ['Fe58',5.33262e-07], + ['Cu63',4.10425995e-05], + ['Cu65',1.8310400499999998e-05], + ['Zn64',2.8360764300000004e-05], + ['Zn66',1.59943867e-05], + ['Zn67',2.3302316e-06], + ['Zn68',1.06417755e-05], + ['Zn70',3.518419e-07]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.514858, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.602996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.585, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4125, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5575, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4665, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5555, bc='interface') +s99 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=400.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-81.662, bc='vacuum') +s20 = mcdc.surface('plane-z', z=81.662, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=76.2, bc='vacuum') + +# Material Cell(s) +c11 = mcdc.cell(-s99, fill=m1) +c12 = mcdc.cell(+s99, fill=m1) +c21 = mcdc.cell(-s1, fill=m2) +c22 = mcdc.cell(+s1 & -s2, fill=m3) +c23 = mcdc.cell(+s2, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Complex Cell(s) Level 1 diff --git a/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-11.py b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-11.py new file mode 100644 index 0000000..65b6cc4 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-11.py @@ -0,0 +1,118 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Water with 1384 PPM Boron +# S(a,b): c_H_in_H2O (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['H1',0.066737], + ['O16',0.033369], + ['B10',1.5359e-05], + ['B11',6.1824e-05]]) +# Material Name: Fuel (2.459 w/o with B-10 for impurities) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00056868], + ['U238',0.022268], + ['O16',0.045682999999999994], + ['B10',2.6055e-07]]) +# Material Name: Aluminum 6061 Cladding for Fuel +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0004900646472], + ['Mg25',6.219614399999999e-05], + ['Mg26',6.84592088e-05], + ['Al27',0.053985], + ['Si28',0.00029725625863999996], + ['Si29',1.5093824679999998e-05], + ['Si30',9.949916679999998e-06], + ['Ti46',3.8991975e-06], + ['Ti47',3.516367199999999e-06], + ['Ti48',3.48422836e-05], + ['Ti49',2.5569283e-06], + ['Ti50',2.4482234e-06], + ['Cr50',2.5213600500000003e-06], + ['Cr52',4.862191881e-05], + ['Cr53',5.51333529e-06], + ['Cr54',1.3723858500000001e-06], + ['Mn55',4.1191e-05], + ['Fe54',1.1052895e-05], + ['Fe56',0.000173506814], + ['Fe57',4.007029e-06], + ['Fe58',5.33262e-07], + ['Cu63',4.10425995e-05], + ['Cu65',1.8310400499999998e-05], + ['Zn64',2.8360764300000004e-05], + ['Zn66',1.59943867e-05], + ['Zn67',2.3302316e-06], + ['Zn68',1.06417755e-05], + ['Zn70',3.518419e-07]]) +# Material Name: Al2O3 +m4 = mcdc.material(nuclides=[ + ['O16',0.023036], + ['Al27',0.015357]]) +# Material Name: Cladding for Al2O3 Perturbing Rods +m5 = mcdc.material(nuclides=[ + ['Mg24',0.0005281663998], + ['Mg25',6.703179599999999e-05], + ['Mg26',7.37818042e-05], + ['Al27',0.058183], + ['Si28',0.000320369016448], + ['Si29',1.6267424576e-05], + ['Si30',1.0723558976e-05], + ['Ti46',4.2024675e-06], + ['Ti47',3.7898616e-06], + ['Ti48',3.75522308e-05], + ['Ti49',2.7557999e-06], + ['Ti50',2.6386402e-06], + ['Cr50',2.7174499e-06], + ['Cr52',5.240331638e-05], + ['Cr53',5.94211542e-06], + ['Cr54',1.4791183e-06], + ['Mn55',4.4395e-05], + ['Fe54',1.191211e-05], + ['Fe56',0.000186994652], + ['Fe57',4.318522e-06], + ['Fe58',5.74716e-07], + ['Cu63',4.4233871999999993e-05], + ['Cu65',1.9734127999999998e-05], + ['Zn64',3.05660388e-05], + ['Zn66',1.7238077199999997e-05], + ['Zn67',2.5114256e-06], + ['Zn68',1.1469257999999999e-05], + ['Zn70',3.792004e-07]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.514858, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.602996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.585, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4125, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5575, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4665, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5555, bc='interface') +s99 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=400.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-81.662, bc='vacuum') +s20 = mcdc.surface('plane-z', z=81.662, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=76.2, bc='vacuum') + +# Material Cell(s) +c11 = mcdc.cell(-s99, fill=m1) +c12 = mcdc.cell(+s99, fill=m1) +c21 = mcdc.cell(-s1, fill=m2) +c22 = mcdc.cell(+s1 & -s2, fill=m3) +c23 = mcdc.cell(+s2, fill=m1) +c51 = mcdc.cell(-s6, fill=m4) +c52 = mcdc.cell(+s6 & -s7, fill=m5) +c53 = mcdc.cell(+s7, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Complex Cell(s) Level 1 diff --git a/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-2.py b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-2.py new file mode 100644 index 0000000..a2f8582 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-2.py @@ -0,0 +1,81 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Water with 1335.5 PPM Boron +# S(a,b): c_H_in_H2O (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['H1',0.066637], + ['O16',0.033369], + ['B10',1.4821e-05], + ['B11',5.9657e-05]]) +# Material Name: Fuel (2.459 w/o with B-10 for impurities) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00056868], + ['U238',0.022268], + ['O16',0.045682999999999994], + ['B10',2.6055e-07]]) +# Material Name: Aluminum 6061 Cladding for Fuel +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0004900646472], + ['Mg25',6.219614399999999e-05], + ['Mg26',6.84592088e-05], + ['Al27',0.053985], + ['Si28',0.00029725625863999996], + ['Si29',1.5093824679999998e-05], + ['Si30',9.949916679999998e-06], + ['Ti46',3.8991975e-06], + ['Ti47',3.516367199999999e-06], + ['Ti48',3.48422836e-05], + ['Ti49',2.5569283e-06], + ['Ti50',2.4482234e-06], + ['Cr50',2.5213600500000003e-06], + ['Cr52',4.862191881e-05], + ['Cr53',5.51333529e-06], + ['Cr54',1.3723858500000001e-06], + ['Mn55',4.1191e-05], + ['Fe54',1.1052895e-05], + ['Fe56',0.000173506814], + ['Fe57',4.007029e-06], + ['Fe58',5.33262e-07], + ['Cu63',4.10425995e-05], + ['Cu65',1.8310400499999998e-05], + ['Zn64',2.8360764300000004e-05], + ['Zn66',1.59943867e-05], + ['Zn67',2.3302316e-06], + ['Zn68',1.06417755e-05], + ['Zn70',3.518419e-07]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.514858, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.602996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.585, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4125, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5575, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4665, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5555, bc='interface') +s99 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=400.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-81.662, bc='vacuum') +s20 = mcdc.surface('plane-z', z=81.662, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=76.2, bc='vacuum') + +# Material Cell(s) +c11 = mcdc.cell(-s99, fill=m1) +c12 = mcdc.cell(+s99, fill=m1) +c21 = mcdc.cell(-s1, fill=m2) +c22 = mcdc.cell(+s1 & -s2, fill=m3) +c23 = mcdc.cell(+s2, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Complex Cell(s) Level 1 diff --git a/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-5.py b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-5.py new file mode 100644 index 0000000..dfab91a --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-5.py @@ -0,0 +1,93 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Water with 1182 PPM Boron +# S(a,b): c_H_in_H2O (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['H1',0.066737], + ['O16',0.033369], + ['B10',1.3118e-05], + ['B11',5.2799999999999996e-05]]) +# Material Name: Fuel (2.459 w/o with B-10 for impurities) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00056868], + ['U238',0.022268], + ['O16',0.045682999999999994], + ['B10',2.6055e-07]]) +# Material Name: Aluminum 6061 Cladding for Fuel +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0004900646472], + ['Mg25',6.219614399999999e-05], + ['Mg26',6.84592088e-05], + ['Al27',0.053985], + ['Si28',0.00029725625863999996], + ['Si29',1.5093824679999998e-05], + ['Si30',9.949916679999998e-06], + ['Ti46',3.8991975e-06], + ['Ti47',3.516367199999999e-06], + ['Ti48',3.48422836e-05], + ['Ti49',2.5569283e-06], + ['Ti50',2.4482234e-06], + ['Cr50',2.5213600500000003e-06], + ['Cr52',4.862191881e-05], + ['Cr53',5.51333529e-06], + ['Cr54',1.3723858500000001e-06], + ['Mn55',4.1191e-05], + ['Fe54',1.1052895e-05], + ['Fe56',0.000173506814], + ['Fe57',4.007029e-06], + ['Fe58',5.33262e-07], + ['Cu63',4.10425995e-05], + ['Cu65',1.8310400499999998e-05], + ['Zn64',2.8360764300000004e-05], + ['Zn66',1.59943867e-05], + ['Zn67',2.3302316e-06], + ['Zn68',1.06417755e-05], + ['Zn70',3.518419e-07]]) +# Material Name: Pyrex +m4 = mcdc.material(nuclides=[ + ['B10',0.00097491], + ['B11',0.0039241], + ['O16',0.044829], + ['Na23',0.0017444], + ['Al27',0.0010018], + ['Si28',0.0168835652208], + ['Si29',0.0008572992695999999], + ['Si30',0.0005651355095999999]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.514858, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.602996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.585, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4125, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5575, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4665, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5555, bc='interface') +s99 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=400.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-81.662, bc='vacuum') +s20 = mcdc.surface('plane-z', z=81.662, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=76.2, bc='vacuum') + +# Material Cell(s) +c11 = mcdc.cell(-s99, fill=m1) +c12 = mcdc.cell(+s99, fill=m1) +c21 = mcdc.cell(-s1, fill=m2) +c22 = mcdc.cell(+s1 & -s2, fill=m3) +c23 = mcdc.cell(+s2, fill=m1) +c31 = mcdc.cell(-s3, fill=m4) +c32 = mcdc.cell(+s3, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Complex Cell(s) Level 1 diff --git a/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-7.py b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-7.py new file mode 100644 index 0000000..2f08eab --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-7.py @@ -0,0 +1,93 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Water with 1032.5 PPM Boron +# S(a,b): c_H_in_H2O (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['H1',0.066737], + ['O16',0.033369], + ['B10',1.1459e-05], + ['B11',4.6122e-05]]) +# Material Name: Fuel (2.459 w/o with B-10 for impurities) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00056868], + ['U238',0.022268], + ['O16',0.045682999999999994], + ['B10',2.6055e-07]]) +# Material Name: Aluminum 6061 Cladding for Fuel +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0004900646472], + ['Mg25',6.219614399999999e-05], + ['Mg26',6.84592088e-05], + ['Al27',0.053985], + ['Si28',0.00029725625863999996], + ['Si29',1.5093824679999998e-05], + ['Si30',9.949916679999998e-06], + ['Ti46',3.8991975e-06], + ['Ti47',3.516367199999999e-06], + ['Ti48',3.48422836e-05], + ['Ti49',2.5569283e-06], + ['Ti50',2.4482234e-06], + ['Cr50',2.5213600500000003e-06], + ['Cr52',4.862191881e-05], + ['Cr53',5.51333529e-06], + ['Cr54',1.3723858500000001e-06], + ['Mn55',4.1191e-05], + ['Fe54',1.1052895e-05], + ['Fe56',0.000173506814], + ['Fe57',4.007029e-06], + ['Fe58',5.33262e-07], + ['Cu63',4.10425995e-05], + ['Cu65',1.8310400499999998e-05], + ['Zn64',2.8360764300000004e-05], + ['Zn66',1.59943867e-05], + ['Zn67',2.3302316e-06], + ['Zn68',1.06417755e-05], + ['Zn70',3.518419e-07]]) +# Material Name: Pyrex +m4 = mcdc.material(nuclides=[ + ['B10',0.00097491], + ['B11',0.0039241], + ['O16',0.044829], + ['Na23',0.0017444], + ['Al27',0.0010018], + ['Si28',0.0168835652208], + ['Si29',0.0008572992695999999], + ['Si30',0.0005651355095999999]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.514858, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.602996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.585, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4125, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5575, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4665, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5555, bc='interface') +s99 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=400.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-81.662, bc='vacuum') +s20 = mcdc.surface('plane-z', z=81.662, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=76.2, bc='vacuum') + +# Material Cell(s) +c11 = mcdc.cell(-s99, fill=m1) +c12 = mcdc.cell(+s99, fill=m1) +c21 = mcdc.cell(-s1, fill=m2) +c22 = mcdc.cell(+s1 & -s2, fill=m3) +c23 = mcdc.cell(+s2, fill=m1) +c31 = mcdc.cell(-s3, fill=m4) +c32 = mcdc.cell(+s3, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Complex Cell(s) Level 1 diff --git a/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-8.py b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-8.py new file mode 100644 index 0000000..44612cf --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/mcdc/leu-comp-therm-008_case-8.py @@ -0,0 +1,93 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Water with 794 PPM Boron +# S(a,b): c_H_in_H2O (Not Implemented) +m1 = mcdc.material(nuclides=[ + ['H1',0.066737], + ['O16',0.033369], + ['B10',8.8117e-06], + ['B11',3.5468e-05]]) +# Material Name: Fuel (2.459 w/o with B-10 for impurities) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00056868], + ['U238',0.022268], + ['O16',0.045682999999999994], + ['B10',2.6055e-07]]) +# Material Name: Aluminum 6061 Cladding for Fuel +m3 = mcdc.material(nuclides=[ + ['Mg24',0.0004900646472], + ['Mg25',6.219614399999999e-05], + ['Mg26',6.84592088e-05], + ['Al27',0.053985], + ['Si28',0.00029725625863999996], + ['Si29',1.5093824679999998e-05], + ['Si30',9.949916679999998e-06], + ['Ti46',3.8991975e-06], + ['Ti47',3.516367199999999e-06], + ['Ti48',3.48422836e-05], + ['Ti49',2.5569283e-06], + ['Ti50',2.4482234e-06], + ['Cr50',2.5213600500000003e-06], + ['Cr52',4.862191881e-05], + ['Cr53',5.51333529e-06], + ['Cr54',1.3723858500000001e-06], + ['Mn55',4.1191e-05], + ['Fe54',1.1052895e-05], + ['Fe56',0.000173506814], + ['Fe57',4.007029e-06], + ['Fe58',5.33262e-07], + ['Cu63',4.10425995e-05], + ['Cu65',1.8310400499999998e-05], + ['Zn64',2.8360764300000004e-05], + ['Zn66',1.59943867e-05], + ['Zn67',2.3302316e-06], + ['Zn68',1.06417755e-05], + ['Zn70',3.518419e-07]]) +# Material Name: Pyrex +m4 = mcdc.material(nuclides=[ + ['B10',0.00097491], + ['B11',0.0039241], + ['O16',0.044829], + ['Na23',0.0017444], + ['Al27',0.0010018], + ['Si28',0.0168835652208], + ['Si29',0.0008572992695999999], + ['Si30',0.0005651355095999999]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.514858, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.602996, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.585, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4125, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5575, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.4665, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5555, bc='interface') +s99 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=400.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-81.662, bc='vacuum') +s20 = mcdc.surface('plane-z', z=81.662, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=76.2, bc='vacuum') + +# Material Cell(s) +c11 = mcdc.cell(-s99, fill=m1) +c12 = mcdc.cell(+s99, fill=m1) +c21 = mcdc.cell(-s1, fill=m2) +c22 = mcdc.cell(+s1 & -s2, fill=m3) +c23 = mcdc.cell(+s2, fill=m1) +c31 = mcdc.cell(-s3, fill=m4) +c32 = mcdc.cell(+s3, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Complex Cell(s) Level 1 diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-1/generate_materials.py b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..ad60ffb --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +water = openmc.Material(name="Water with 1511 PPM") +water.add_nuclide('H1', 6.6737e-02) +water.add_nuclide('O16', 3.3369e-02) +water.add_nuclide('B10', 1.6769e-05) +water.add_nuclide('B11', 6.7497e-05) +water.add_s_alpha_beta('c_H_in_H2O') + +fuel = openmc.Material(name="Fuel (2.459 w/o with B-10 for impurities)") +fuel.add_nuclide('U234', 4.5689e-06) +fuel.add_nuclide('U235', 5.6868e-04) +fuel.add_nuclide('U238', 2.2268e-02) +fuel.add_nuclide('O16', 4.5683e-02) +fuel.add_nuclide('B10', 2.6055e-07) + +aluminum = openmc.Material(name="Aluminum 6061 Cladding for Fuel") +aluminum.add_element('Mg', 6.2072e-04) +aluminum.add_element('Al', 5.3985e-02) +aluminum.add_element('Si', 3.2230e-04) +aluminum.add_element('Ti', 4.7263e-05) +aluminum.add_element('Cr', 5.8029e-05) +aluminum.add_element('Mn', 4.1191e-05) +aluminum.add_element('Fe', 1.8910e-04) +aluminum.add_element('Cu', 5.9353e-05) +aluminum.add_element('Zn', 5.7679e-05) + +materials = openmc.Materials([water, fuel, aluminum]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-1/geometry.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/geometry.xml new file mode 100644 index 0000000..526eaf2 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/geometry.xml @@ -0,0 +1,602 @@ + + + + + + + + -12.2682 -12.2682 + 1.63576 1.63576 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 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+ 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + + + + + + + + + + + + + + + -85.8774 -85.8774 + 24.5364 24.5364 + + 999 999 130 140 150 999 999 + 999 220 230 240 250 260 999 + 130 320 111 111 111 360 150 + 410 240 111 111 111 240 470 + 510 520 111 111 111 560 570 + 999 620 630 240 650 660 999 + 999 999 510 740 570 999 999 + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/materials.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/materials.xml new file mode 100644 index 0000000..3abc61c --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/plots.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/plots.xml new file mode 100644 index 0000000..b3b2dcc --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/plots.xml @@ -0,0 +1,31 @@ + + + + + + + 0.0 0.0 0.0 + 155 155 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/settings.xml new file mode 100644 index 0000000..74ab4de --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/original/settings.xml @@ -0,0 +1,23 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + box + + -10.0 -10.0 -81.662 + 10.0 10.0 81.662 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-1/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/settings.xml new file mode 100644 index 0000000..f5a50b6 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-1/settings.xml @@ -0,0 +1,17 @@ + + + + + eigenvalue + 200 + 20 + 10000 + + + + + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-11/generate_materials.py b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/generate_materials.py new file mode 100644 index 0000000..220c025 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/generate_materials.py @@ -0,0 +1,45 @@ +import openmc + +water = openmc.Material(name="Water with 1384 PPM Boron") +water.add_nuclide('H1', 6.6737e-02) +water.add_nuclide('O16', 3.3369e-02) +water.add_nuclide('B10', 1.5359e-05) +water.add_nuclide('B11', 6.1824e-05) +water.add_s_alpha_beta('c_H_in_H2O') + +fuel = openmc.Material(name="Fuel (2.459 w/o with B-10 for impurities)") +fuel.add_nuclide('U234', 4.5689e-06) +fuel.add_nuclide('U235', 5.6868e-04) +fuel.add_nuclide('U238', 2.2268e-02) +fuel.add_nuclide('O16', 4.5683e-02) +fuel.add_nuclide('B10', 2.6055e-07) + +aluminum = openmc.Material(name="Aluminum 6061 Cladding for Fuel") +aluminum.add_element('Mg', 6.2072e-04) +aluminum.add_element('Al', 5.3985e-02) +aluminum.add_element('Si', 3.2230e-04) +aluminum.add_element('Ti', 4.7263e-05) +aluminum.add_element('Cr', 5.8029e-05) +aluminum.add_element('Mn', 4.1191e-05) +aluminum.add_element('Fe', 1.8910e-04) +aluminum.add_element('Cu', 5.9353e-05) +aluminum.add_element('Zn', 5.7679e-05) + +al2o3 = openmc.Material(name="Al2O3") +al2o3.set_density('sum') +al2o3.add_nuclide('O16', 2.3036e-02) +al2o3.add_nuclide('Al27', 1.5357e-02) + +cladding = openmc.Material(name="Cladding for Al2O3 Perturbing Rods") +cladding.add_element('Mg', 6.6898e-04) +cladding.add_element('Al', 5.8183e-02) +cladding.add_element('Si', 3.4736e-04) +cladding.add_element('Ti', 5.0939e-05) +cladding.add_element('Cr', 6.2542e-05) +cladding.add_element('Mn', 4.4395e-05) +cladding.add_element('Fe', 2.0380e-04) +cladding.add_element('Cu', 6.3968e-05) +cladding.add_element('Zn', 6.2164e-05) + +materials = openmc.Materials([water, fuel, aluminum, al2o3, cladding]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-11/geometry.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/geometry.xml new file mode 100644 index 0000000..175ae90 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/geometry.xml @@ -0,0 +1,608 @@ + + + + + + + + -12.2682 -12.2682 + 1.63576 1.63576 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 5 2 2 2 5 2 2 2 2 2 + 2 2 2 5 2 2 2 2 2 2 2 5 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 5 2 2 5 2 2 2 5 2 2 5 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 1 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 5 2 2 5 2 2 2 5 2 2 5 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 5 2 2 2 2 2 2 2 5 2 2 2 + 2 2 2 2 2 5 2 2 2 5 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + 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a/icsbep/openmc/leu-comp-therm-008/openmc/case-11/plots.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/plots.xml new file mode 100644 index 0000000..7236532 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/plots.xml @@ -0,0 +1,31 @@ + + + + + + + 0.0 0.0 0.0 + 155 155 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-11/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/settings.xml new file mode 100644 index 0000000..74ab4de --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-11/settings.xml @@ -0,0 +1,23 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + box + + -10.0 -10.0 -81.662 + 10.0 10.0 81.662 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-2/generate_materials.py b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..3f65f5b --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +water = openmc.Material(name="Water with 1335.5 PPM Boron") +water.add_nuclide('H1', 6.6637e-02) +water.add_nuclide('O16', 3.3369e-02) +water.add_nuclide('B10', 1.4821e-05) +water.add_nuclide('B11', 5.9657e-05) +water.add_s_alpha_beta('c_H_in_H2O') + +fuel = openmc.Material(name="Fuel (2.459 w/o with B-10 for impurities)") +fuel.add_nuclide('U234', 4.5689e-06) +fuel.add_nuclide('U235', 5.6868e-04) +fuel.add_nuclide('U238', 2.2268e-02) +fuel.add_nuclide('O16', 4.5683e-02) +fuel.add_nuclide('B10', 2.6055e-07) + +aluminum = openmc.Material(name="Aluminum 6061 Cladding for Fuel") +aluminum.add_element('Mg', 6.2072e-04) +aluminum.add_element('Al', 5.3985e-02) +aluminum.add_element('Si', 3.2230e-04) +aluminum.add_element('Ti', 4.7263e-05) +aluminum.add_element('Cr', 5.8029e-05) +aluminum.add_element('Mn', 4.1191e-05) +aluminum.add_element('Fe', 1.8910e-04) +aluminum.add_element('Cu', 5.9353e-05) +aluminum.add_element('Zn', 5.7679e-05) + +materials = openmc.Materials([water, fuel, aluminum]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-2/geometry.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/geometry.xml new file mode 100644 index 0000000..fee1691 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/geometry.xml @@ -0,0 +1,600 @@ + + + + + + + + -12.2682 -12.2682 + 1.63576 1.63576 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 1 2 2 2 1 2 2 2 2 2 + 2 2 2 1 2 2 2 2 2 2 2 1 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 1 2 2 1 2 2 2 1 2 2 1 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 1 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 1 2 2 1 2 2 2 1 2 2 1 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 1 2 2 2 2 2 2 2 1 2 2 2 + 2 2 2 2 2 1 2 2 2 1 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + 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1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + + + + + + + + + + + + + + + -85.8774 -85.8774 + 24.5364 24.5364 + + 999 999 130 140 150 999 999 + 999 220 230 240 250 260 999 + 130 320 111 111 111 360 150 + 410 240 111 111 111 240 470 + 510 520 111 111 111 560 570 + 999 620 630 240 650 660 999 + 999 999 510 740 570 999 999 + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-2/materials.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/materials.xml new file mode 100644 index 0000000..138fe78 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/materials.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-2/plots.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/plots.xml new file mode 100644 index 0000000..bf10dac --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/plots.xml @@ -0,0 +1,31 @@ + + + + + + + 0.0 0.0 0.0 + 155 155 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-2/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/settings.xml new file mode 100644 index 0000000..74ab4de --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-2/settings.xml @@ -0,0 +1,23 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + box + + -10.0 -10.0 -81.662 + 10.0 10.0 81.662 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-5/generate_materials.py b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..4bfed09 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +water = openmc.Material(name="Water with 1182 PPM Boron") +water.add_nuclide('H1', 6.6737e-02) +water.add_nuclide('O16', 3.3369e-02) +water.add_nuclide('B10', 1.3118e-05) +water.add_nuclide('B11', 5.2800e-05) +water.add_s_alpha_beta('c_H_in_H2O') + +fuel = openmc.Material(name="Fuel (2.459 w/o with B-10 for impurities)") +fuel.add_nuclide('U234', 4.5689e-06) +fuel.add_nuclide('U235', 5.6868e-04) +fuel.add_nuclide('U238', 2.2268e-02) +fuel.add_nuclide('O16', 4.5683e-02) +fuel.add_nuclide('B10', 2.6055e-07) + +aluminum = openmc.Material(name="Aluminum 6061 Cladding for Fuel") +aluminum.add_element('Mg', 6.2072e-04) +aluminum.add_element('Al', 5.3985e-02) +aluminum.add_element('Si', 3.2230e-04) +aluminum.add_element('Ti', 4.7263e-05) +aluminum.add_element('Cr', 5.8029e-05) +aluminum.add_element('Mn', 4.1191e-05) +aluminum.add_element('Fe', 1.8910e-04) +aluminum.add_element('Cu', 5.9353e-05) +aluminum.add_element('Zn', 5.7679e-05) + +pyrex = openmc.Material(name="Pyrex") +pyrex.add_nuclide('B10', 9.7491e-04) +pyrex.add_nuclide('B11', 3.9241e-03) +pyrex.add_nuclide('O16', 4.4829e-02) +pyrex.add_nuclide('Na23', 1.7444e-03) +pyrex.add_nuclide('Al27', 1.0018e-03) +pyrex.add_element('Si', 1.8306e-02) + +materials = openmc.Materials([water, fuel, aluminum, pyrex]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-5/geometry.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/geometry.xml new file mode 100644 index 0000000..413429f --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/geometry.xml @@ -0,0 +1,606 @@ + + + + + + + + -12.2682 -12.2682 + 1.63576 1.63576 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 1 2 2 2 1 2 2 2 2 2 + 2 2 2 3 2 2 2 2 2 2 2 3 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 1 2 2 1 2 2 2 1 2 2 1 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 1 2 2 2 2 2 2 2 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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + + + + + + + + + + + + + + + -85.8774 -85.8774 + 24.5364 24.5364 + + 999 999 130 140 150 999 999 + 999 220 230 240 250 260 999 + 130 320 111 111 111 360 150 + 410 240 111 111 111 240 470 + 510 520 111 111 111 560 570 + 999 620 630 240 650 660 999 + 999 999 510 740 570 999 999 + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-5/materials.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/materials.xml new file mode 100644 index 0000000..15d437a --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/materials.xml @@ -0,0 +1,61 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-5/plots.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/plots.xml new file mode 100644 index 0000000..ad59fa0 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/plots.xml @@ -0,0 +1,31 @@ + + + + + + + 0.0 0.0 0.0 + 155 155 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-5/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/settings.xml new file mode 100644 index 0000000..74ab4de --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-5/settings.xml @@ -0,0 +1,23 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + box + + -10.0 -10.0 -81.662 + 10.0 10.0 81.662 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-7/generate_materials.py b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..99b8275 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +water = openmc.Material(name="Water with 1032.5 PPM Boron") +water.add_nuclide('H1', 6.6737e-02) +water.add_nuclide('O16', 3.3369e-02) +water.add_nuclide('B10', 1.1459e-05) +water.add_nuclide('B11', 4.6122e-05) +water.add_s_alpha_beta('c_H_in_H2O') + +fuel = openmc.Material(name="Fuel (2.459 w/o with B-10 for impurities)") +fuel.add_nuclide('U234', 4.5689e-06) +fuel.add_nuclide('U235', 5.6868e-04) +fuel.add_nuclide('U238', 2.2268e-02) +fuel.add_nuclide('O16', 4.5683e-02) +fuel.add_nuclide('B10', 2.6055e-07) + +aluminum = openmc.Material(name="Aluminum 6061 Cladding for Fuel") +aluminum.add_element('Mg', 6.2072e-04) +aluminum.add_element('Al', 5.3985e-02) +aluminum.add_element('Si', 3.2230e-04) +aluminum.add_element('Ti', 4.7263e-05) +aluminum.add_element('Cr', 5.8029e-05) +aluminum.add_element('Mn', 4.1191e-05) +aluminum.add_element('Fe', 1.8910e-04) +aluminum.add_element('Cu', 5.9353e-05) +aluminum.add_element('Zn', 5.7679e-05) + +pyrex = openmc.Material(name="Pyrex") +pyrex.add_nuclide('B10', 9.7491e-04) +pyrex.add_nuclide('B11', 3.9241e-03) +pyrex.add_nuclide('O16', 4.4829e-02) +pyrex.add_nuclide('Na23', 1.7444e-03) +pyrex.add_nuclide('Al27', 1.0018e-03) +pyrex.add_element('Si', 1.8306e-02) + +materials = openmc.Materials([water, fuel, aluminum, pyrex]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-7/geometry.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/geometry.xml new file mode 100644 index 0000000..f16ea0b --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/geometry.xml @@ -0,0 +1,606 @@ + + + + + + + + -12.2682 -12.2682 + 1.63576 1.63576 + + 2 2 2 2 2 2 2 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+ + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-7/materials.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/materials.xml new file mode 100644 index 0000000..966d38b --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/materials.xml @@ -0,0 +1,61 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-7/plots.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/plots.xml new file mode 100644 index 0000000..b435be4 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/plots.xml @@ -0,0 +1,31 @@ + + + + + + + 0.0 0.0 0.0 + 155 155 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-7/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/settings.xml new file mode 100644 index 0000000..74ab4de --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-7/settings.xml @@ -0,0 +1,23 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + box + + -10.0 -10.0 -81.662 + 10.0 10.0 81.662 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-8/generate_materials.py b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..7e393e7 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +water = openmc.Material(name="Water with 794 PPM Boron") +water.add_nuclide('H1', 6.6737e-02) +water.add_nuclide('O16', 3.3369e-02) +water.add_nuclide('B10', 8.8117e-06) +water.add_nuclide('B11', 3.5468e-05) +water.add_s_alpha_beta('c_H_in_H2O') + +fuel = openmc.Material(name="Fuel (2.459 w/o with B-10 for impurities)") +fuel.add_nuclide('U234', 4.5689e-06) +fuel.add_nuclide('U235', 5.6868e-04) +fuel.add_nuclide('U238', 2.2268e-02) +fuel.add_nuclide('O16', 4.5683e-02) +fuel.add_nuclide('B10', 2.6055e-07) + +aluminum = openmc.Material(name="Aluminum 6061 Cladding for Fuel") +aluminum.add_element('Mg', 6.2072e-04) +aluminum.add_element('Al', 5.3985e-02) +aluminum.add_element('Si', 3.2230e-04) +aluminum.add_element('Ti', 4.7263e-05) +aluminum.add_element('Cr', 5.8029e-05) +aluminum.add_element('Mn', 4.1191e-05) +aluminum.add_element('Fe', 1.8910e-04) +aluminum.add_element('Cu', 5.9353e-05) +aluminum.add_element('Zn', 5.7679e-05) + +pyrex = openmc.Material(name="Pyrex") +pyrex.add_nuclide('B10', 9.7491e-04) +pyrex.add_nuclide('B11', 3.9241e-03) +pyrex.add_nuclide('O16', 4.4829e-02) +pyrex.add_nuclide('Na23', 1.7444e-03) +pyrex.add_nuclide('Al27', 1.0018e-03) +pyrex.add_element('Si', 1.8306e-02) + +materials = openmc.Materials([water, fuel, aluminum, pyrex]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-8/geometry.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/geometry.xml 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999 999 130 140 150 999 999 + 999 220 230 240 250 260 999 + 130 320 111 111 111 360 150 + 410 240 111 111 111 240 470 + 510 520 111 111 111 560 570 + 999 620 630 240 650 660 999 + 999 999 510 740 570 999 999 + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-8/materials.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/materials.xml new file mode 100644 index 0000000..c596a50 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/materials.xml @@ -0,0 +1,61 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-8/plots.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/plots.xml new file mode 100644 index 0000000..7aca8c4 --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/plots.xml @@ -0,0 +1,31 @@ + + + + + + + 0.0 0.0 0.0 + 155 155 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + + 0.0 0.0 0.0 + 200 200 + 1000 1000 + + + diff --git a/icsbep/openmc/leu-comp-therm-008/openmc/case-8/settings.xml b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/settings.xml new file mode 100644 index 0000000..74ab4de --- /dev/null +++ b/icsbep/openmc/leu-comp-therm-008/openmc/case-8/settings.xml @@ -0,0 +1,23 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + box + + -10.0 -10.0 -81.662 + 10.0 10.0 81.662 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-001/mcdc/leu-sol-therm-001.py b/icsbep/openmc/leu-sol-therm-001/mcdc/leu-sol-therm-001.py new file mode 100644 index 0000000..ce6e1ec --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-001/mcdc/leu-sol-therm-001.py @@ -0,0 +1,85 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: SS304L +m1 = mcdc.material(nuclides=[ + ['Cr50',0.0007103206000000001], + ['Cr52',0.013697825720000001], + ['Cr53',0.00155322348], + ['Cr54',0.00038663020000000007], + ['Mn55',0.0017192], + ['Fe54',0.0035092211000000003], + ['Fe56',0.055087266520000004], + ['Fe57',0.00127220522], + ['Fe58',0.00016930716], + ['Ni58',0.0049299929442], + ['Ni60',0.0018990244557999995], + ['Ni61',8.25492782e-05], + ['Ni62',0.000263203221], + ['Ni64',6.70301008e-05]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['N14',3.5085011118e-05], + ['N15',1.2898888199999999e-07], + ['O16',1.5086280132e-05], + ['O17',5.719868e-09]]) +# Material Name: Fuel Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.00012377], + ['U238',0.0023508], + ['H1',0.056179], + ['O16',0.032954505507], + ['O17',1.2494493000000001e-05], + ['F19',0.0051035]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-40.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=-37.1425, bc='interface') +s3 = mcdc.surface('plane-z', z=7.6575, bc='interface') +s4 = mcdc.surface('plane-z', z=39.375, bc='interface') +s5 = mcdc.surface('plane-z', z=41.28, bc='vacuum') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.54, bc='interface') +s7 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.175, bc='interface') +s8 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=24.4475, bc='interface') +s9 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=25.4, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s6, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s6 & -s9, fill=m1) +c3 = mcdc.cell(+s2 & -s4 & -s6, fill=m2) +c4 = mcdc.cell(+s2 & -s4 & +s6 & -s7, fill=m1) +c5 = mcdc.cell(+s2 & -s3 & +s7 & -s8, fill=m3) +c6 = mcdc.cell(+s3 & -s4 & +s7 & -s8, fill=m2) +c7 = mcdc.cell(+s2 & -s4 & +s8 & -s9, fill=m1) +c8 = mcdc.cell(+s4 & -s5 & -s6, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s6 & -s9, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-10.0,10.0], y=[-10.0,10.0], z=[-40.0,40.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-001/openmc/generate_materials.py b/icsbep/openmc/leu-sol-therm-001/openmc/generate_materials.py new file mode 100644 index 0000000..9b47cd1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-001/openmc/generate_materials.py @@ -0,0 +1,34 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "SS304L" +mat.set_density('sum') +mat.add_element('Cr', 1.6348e-02) +mat.add_element('Mn', 1.7192e-03) +mat.add_element('Fe', 6.0038e-02) +mat.add_element('Ni', 7.2418e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.5214e-05) +mat.add_element('O', 1.5092e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Fuel Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.7855e-07) +mat.add_nuclide('U235', 1.2377e-04) +mat.add_nuclide('U236', 1.2085e-06) +mat.add_nuclide('U238', 2.3508e-03) +mat.add_nuclide('H1', 5.6179e-02) +mat.add_element('O', 3.2967e-02) +mat.add_element('F', 5.1035e-03) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-001/openmc/geometry.xml b/icsbep/openmc/leu-sol-therm-001/openmc/geometry.xml new file mode 100644 index 0000000..31aae71 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-001/openmc/geometry.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-001/openmc/materials.xml b/icsbep/openmc/leu-sol-therm-001/openmc/materials.xml new file mode 100644 index 0000000..9c821b1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-001/openmc/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-001/openmc/settings.xml b/icsbep/openmc/leu-sol-therm-001/openmc/settings.xml new file mode 100644 index 0000000..65061d5 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -10 -10 -40 10 10 40 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-1.py b/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-1.py new file mode 100644 index 0000000..611456f --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-1.py @@ -0,0 +1,71 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.6655e-05], + ['U238',0.0010878], + ['F19',0.0022893], + ['O16',0.033389340642], + ['O17',1.2659357999999998e-05], + ['H1',0.062226]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.5578, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=49.5578, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-2.py b/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-2.py new file mode 100644 index 0000000..7c62c39 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-2.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.1604e-05], + ['U238',0.0011828], + ['F19',0.0024893], + ['O16',0.033318367551], + ['O17',1.2632448999999999e-05], + ['H1',0.061683]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.4995, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.6583, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-3.py b/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-3.py new file mode 100644 index 0000000..53ff5ca --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/mcdc/leu-sol-therm-002_case-3.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranium Oxyfluoride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.1604e-05], + ['U238',0.0011828], + ['F19',0.0024893], + ['O16',0.033318367551], + ['O17',1.2632448999999999e-05], + ['H1',0.061683]]) +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059699], + ['Si28',0.000509126279536], + ['Si29',2.5851979831999998e-05], + ['Si30',1.7041740632e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853e-05]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066659], + ['O16',0.033316368309], + ['O17',1.2631690999999997e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.671, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.8298, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=49.8298, bc='vacuum') +s4 = mcdc.surface('plane-z', z=16.7413, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(-s1 & +s4, fill=mvoid) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-1/generate_materials.py b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..4452015 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 2.3271e-07) +mat.add_nuclide('U235', 5.6655e-05) +mat.add_nuclide('U238', 1.0878e-03) +mat.add_element('F', 2.2893e-03) +mat.add_element('O', 3.3402e-02) +mat.add_nuclide('H1', 6.2226e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-1/geometry.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/geometry.xml new file mode 100644 index 0000000..20babf2 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-1/materials.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/materials.xml new file mode 100644 index 0000000..8ed6013 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/materials.xml @@ -0,0 +1,36 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-1/settings.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-2/generate_materials.py b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..c29de87 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5304e-07) +mat.add_nuclide('U235', 6.1604e-05) +mat.add_nuclide('U238', 1.1828e-03) +mat.add_element('F', 2.4893e-03) +mat.add_element('O', 3.3331e-02) +mat.add_nuclide('H1', 6.1683e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-2/geometry.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/geometry.xml new file mode 100644 index 0000000..a257708 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-2/materials.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/materials.xml new file mode 100644 index 0000000..ea00fe0 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/materials.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-2/settings.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-3/generate_materials.py b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..a5e449e --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranium Oxyfluoride Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 2.5304e-07) +mat.add_nuclide('U235', 6.1604e-05) +mat.add_nuclide('U238', 1.1828e-03) +mat.add_element('F', 2.4893e-03) +mat.add_element('O', 3.3331e-02) +mat.add_nuclide('H1', 6.1683e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9699e-02) +mat.add_element('Si', 5.5202e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6659e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-3/geometry.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/geometry.xml new file mode 100644 index 0000000..25e7c16 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-3/materials.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/materials.xml new file mode 100644 index 0000000..e8769ae --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/materials.xml @@ -0,0 +1,36 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-002/openmc/case-3/settings.xml b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-002/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-1.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-1.py new file mode 100644 index 0000000..6d75b89 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-1.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.6403e-05], + ['U238',0.00067271], + ['N14',0.0023185], + ['O16',0.037458797732999996], + ['O17',1.4202266999999998e-05], + ['H1',0.05885399999999999]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=32.9537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=33.1037, bc='vacuum') +s3 = mcdc.surface('plane-z', z=16.4073, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(-s1 & +s3, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-2.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-2.py new file mode 100644 index 0000000..3c9a869 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-2.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.8143e-05], + ['U238',0.00059998], + ['N14',0.002054], + ['O16',0.037027961081999995], + ['O17',1.4038918e-05], + ['H1',0.059801999999999994]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=32.9537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=33.1037, bc='vacuum') +s3 = mcdc.surface('plane-z', z=25.1548, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(-s1 & +s3, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-3.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-3.py new file mode 100644 index 0000000..17ec3ec --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-3.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.7111e-05], + ['U238',0.00059089], + ['N14',0.0019856], + ['O16',0.037025961839999996], + ['O17',1.4038159999999996e-05], + ['H1',0.06019900000000001]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=32.9537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=33.1037, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-4.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-4.py new file mode 100644 index 0000000..6805cfc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-4.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.582e-05], + ['U238',0.00057953], + ['N14',0.0019783], + ['O16',0.036925000119], + ['O17',1.3999881e-05], + ['H1',0.06011]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.6303, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.8203, bc='vacuum') +s3 = mcdc.surface('plane-z', z=3.9656, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(-s1 & +s3, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-5.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-5.py new file mode 100644 index 0000000..b9039d0 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-5.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.2398e-05], + ['U238',0.00046135], + ['N14',0.0015764], + ['O16',0.036211270725], + ['O17',1.3729275e-05], + ['H1',0.061483]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.6303, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.8203, bc='vacuum') +s3 = mcdc.surface('plane-z', z=28.0537, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(-s1 & +s3, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-6.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-6.py new file mode 100644 index 0000000..63f4fe6 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-6.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.0849e-05], + ['U238',0.00044771], + ['N14',0.001534], + ['O16',0.036161289675], + ['O17',1.3710325e-05], + ['H1',0.061685000000000004]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.6303, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=43.8203, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-7.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-7.py new file mode 100644 index 0000000..babf17e --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-7.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.981700000000001e-05], + ['U238',0.00043862], + ['N14',0.0015077], + ['O16',0.036103311657], + ['O17',1.3688343e-05], + ['H1',0.061763]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=59.8897, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.0997, bc='vacuum') +s3 = mcdc.surface('plane-z', z=4.6151, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(-s1 & +s3, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-8.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-8.py new file mode 100644 index 0000000..f62f26f --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-8.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.4138e-05], + ['U238',0.00038862], + ['N14',0.0013661], + ['O16',0.035854406028], + ['O17',1.3593971999999999e-05], + ['H1',0.06230700000000001]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=59.8897, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.0997, bc='vacuum') +s3 = mcdc.surface('plane-z', z=41.934, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(-s1 & +s3, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-9.py b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-9.py new file mode 100644 index 0000000..488b8f8 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/mcdc/leu-sol-therm-003_case-9.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',4.3364e-05], + ['U238',0.00038181], + ['N14',0.0013569], + ['O16',0.035823417777], + ['O17',1.3582222999999998e-05], + ['H1',0.062336]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0034536936], + ['Fe56',0.05421560352], + ['Fe57',0.00125207472], + ['Fe58',0.00016662816], + ['Cr50',0.0007183154000000001], + ['Cr52',0.013851997480000001], + ['Cr53',0.0015707053200000002], + ['Cr54',0.00039098180000000005], + ['Ni58',0.055393492760999995], + ['Ni60',0.021337474239], + ['Ni61',0.000927525231], + ['Ni62',0.002957356305], + ['Ni64',0.000753151464], + ['Mn55',0.013039], + ['Si28',0.0125460033704], + ['Si29',0.0006370502548], + ['Si30',0.0004199463748], + ['Ti46',0.0049371300000000005], + ['Ti47',0.0044523936], + ['Ti48',0.0441169968], + ['Ti49',0.0032375604], + ['Ti50',0.0030999192]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=59.8897, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.0997, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-1/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..57fc98f --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.7481e-07) +mat.add_nuclide('U235', 7.6403e-05) +mat.add_nuclide('U238', 6.7271e-04) +mat.add_nuclide('N14', 2.3185e-03) +mat.add_element('O', 3.7473e-02) +mat.add_nuclide('H1', 5.8854e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-1/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/geometry.xml new file mode 100644 index 0000000..243b37a --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-1/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/materials.xml new file mode 100644 index 0000000..afa2099 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-1/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-1/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-2/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..d2057f7 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.0186e-07) +mat.add_nuclide('U235', 6.8143e-05) +mat.add_nuclide('U238', 5.9998e-04) +mat.add_nuclide('N14', 2.0540e-03) +mat.add_element('O', 3.7042e-02) +mat.add_nuclide('H1', 5.9802e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-2/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/geometry.xml new file mode 100644 index 0000000..e406b56 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-2/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/materials.xml new file mode 100644 index 0000000..5f0c091 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-2/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-2/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-3/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..5c2a3a7 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.9274e-07) +mat.add_nuclide('U235', 6.7111e-05) +mat.add_nuclide('U238', 5.9089e-04) +mat.add_nuclide('N14', 1.9856e-03) +mat.add_element('O', 3.7040e-02) +mat.add_nuclide('H1', 6.0199e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-3/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/geometry.xml new file mode 100644 index 0000000..3e11af2 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-3/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/materials.xml new file mode 100644 index 0000000..5308410 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-3/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-3/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-4/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..7c0e0ce --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.8134e-07) +mat.add_nuclide('U235', 6.5820e-05) +mat.add_nuclide('U238', 5.7953e-04) +mat.add_nuclide('N14', 1.9783e-03) +mat.add_element('O', 3.6939e-02) +mat.add_nuclide('H1', 6.0110e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-4/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/geometry.xml new file mode 100644 index 0000000..ad8bd04 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-4/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/materials.xml new file mode 100644 index 0000000..43e197d --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-4/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-4/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-5/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..5dd7ff7 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.6279e-07) +mat.add_nuclide('U235', 5.2398e-05) +mat.add_nuclide('U238', 4.6135e-04) +mat.add_nuclide('N14', 1.5764e-03) +mat.add_element('O', 3.6225e-02) +mat.add_nuclide('H1', 6.1483e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-5/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/geometry.xml new file mode 100644 index 0000000..68fcb1b --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-5/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/materials.xml new file mode 100644 index 0000000..44ac216 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-5/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-5/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-6/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..d77359a --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.4911e-07) +mat.add_nuclide('U235', 5.0849e-05) +mat.add_nuclide('U238', 4.4771e-04) +mat.add_nuclide('N14', 1.5340e-03) +mat.add_element('O', 3.6175e-02) +mat.add_nuclide('H1', 6.1685e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-6/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/geometry.xml new file mode 100644 index 0000000..c02f66a --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-6/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/materials.xml new file mode 100644 index 0000000..2cc3eb9 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-6/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-6/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-7/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..9f9c4c1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.3999e-07) +mat.add_nuclide('U235', 4.9817e-05) +mat.add_nuclide('U238', 4.3862e-04) +mat.add_nuclide('N14', 1.5077e-03) +mat.add_element('O', 3.6117e-02) +mat.add_nuclide('H1', 6.1763e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-7/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/geometry.xml new file mode 100644 index 0000000..327b14c --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-7/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/materials.xml new file mode 100644 index 0000000..0ce57d3 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-7/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-7/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-8/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..a9e515c --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8984e-07) +mat.add_nuclide('U235', 4.4138e-05) +mat.add_nuclide('U238', 3.8862e-04) +mat.add_nuclide('N14', 1.3661e-03) +mat.add_element('O', 3.5868e-02) +mat.add_nuclide('H1', 6.2307e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-8/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/geometry.xml new file mode 100644 index 0000000..3f25417 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-8/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/materials.xml new file mode 100644 index 0000000..0cd54e8 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-8/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-8/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-9/generate_materials.py b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..7e714fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 3.8300e-07) +mat.add_nuclide('U235', 4.3364e-05) +mat.add_nuclide('U238', 3.8181e-04) +mat.add_nuclide('N14', 1.3569e-03) +mat.add_element('O', 3.5837e-02) +mat.add_nuclide('H1', 6.2336e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9088e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 8.1369e-02) +mat.add_element('Mn', 1.3039e-02) +mat.add_element('Si', 1.3603e-02) +mat.add_element('Ti', 5.9844e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-9/geometry.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/geometry.xml new file mode 100644 index 0000000..7390267 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-9/materials.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/materials.xml new file mode 100644 index 0000000..17901d3 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/materials.xml @@ -0,0 +1,39 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-003/openmc/case-9/settings.xml b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-003/openmc/case-9/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-1.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-1.py new file mode 100644 index 0000000..4d85a69 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-1.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.9213e-05], + ['U238',0.00070556], + ['H1',0.056956], + ['N14',0.0028778], + ['O16',0.038014587009], + ['O17',1.4412991e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=41.53, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-29.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-29.py new file mode 100644 index 0000000..aa24416 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-29.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.4181e-05], + ['U238',0.00066074], + ['H1',0.057215999999999996], + ['N14',0.0028141], + ['O16',0.037835654850000004], + ['O17',1.4345150000000001e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=46.7, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-33.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-33.py new file mode 100644 index 0000000..fef03f8 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-33.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.897e-05], + ['U238',0.00061432], + ['H1',0.058085], + ['N14',0.0026927], + ['O16',0.037811663945999996], + ['O17',1.4336053999999999e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=52.93, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-34.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-34.py new file mode 100644 index 0000000..c2edd73 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-34.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.478e-05], + ['U238',0.00057701], + ['H1',0.05803199999999999], + ['N14',0.0026337], + ['O16',0.037512777266999996], + ['O17',1.4222733e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=64.85, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-46.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-46.py new file mode 100644 index 0000000..45ad702 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-46.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.1792e-05], + ['U238',0.00055039], + ['H1',0.058189], + ['N14',0.0025925], + ['O16',0.037399820094], + ['O17',1.4179906000000003e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=78.56, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-51.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-51.py new file mode 100644 index 0000000..9ba3295 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-51.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.956899999999999e-05], + ['U238',0.00053059], + ['H1',0.058528], + ['N14',0.0025544], + ['O16',0.037407817062], + ['O17',1.4182938e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=95.5, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-54.py b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-54.py new file mode 100644 index 0000000..626ada5 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/mcdc/leu-sol-therm-004_case-54.py @@ -0,0 +1,99 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',5.7551e-05], + ['U238',0.00051262], + ['H1',0.058561], + ['N14',0.0025144], + ['O16',0.037263871638], + ['O17',1.4128362000000001e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',4.3736e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',1.3170000000000001e-05], + ['S32',1.88009591868e-06], + ['S33',1.4810585579999998e-08], + ['S34',8.300507418e-08], + ['S36',2.8842156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.507107969999999e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.054521144339999994], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=59.8, bc='vacuum') +s4 = mcdc.surface('plane-z', z=-32.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-2.0, bc='interface') +s6 = mcdc.surface('plane-z', z=0.0, bc='interface') +s7 = mcdc.surface('plane-z', z=130.33, bc='interface') +s8 = mcdc.surface('plane-z', z=150.0, bc='interface') +s9 = mcdc.surface('plane-z', z=152.5, bc='interface') +s10 = mcdc.surface('plane-z', z=172.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s4 & -s5 & -s3, fill=m3) +c2 = mcdc.cell(+s5 & -s6 & -s1, fill=m2) +c3 = mcdc.cell(+s6 & -s7 & -s1, fill=m1) +c4 = mcdc.cell(+s7 & -s8 & -s1, fill=m4) +c5 = mcdc.cell(+s8 & -s9 & -s1, fill=m2) +c6 = mcdc.cell(+s5 & -s9 & +s1 & -s2, fill=m2) +c7 = mcdc.cell(+s5 & -s9 & +s2 & -s3, fill=m3) +c8 = mcdc.cell(+s9 & -s10 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-1/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..49b7d21 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.3833e-07) +mat.add_nuclide('U235', 7.9213e-05) +mat.add_nuclide('U236', 7.9114e-08) +mat.add_nuclide('U238', 7.0556e-04) +mat.add_nuclide('H1', 5.6956e-02) +mat.add_nuclide('N14', 2.8778e-03) +mat.add_element('O', 3.8029e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-1/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/geometry.xml new file mode 100644 index 0000000..b944039 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-1/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/materials.xml new file mode 100644 index 0000000..4d37e12 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-1/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-1/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-29/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/generate_materials.py new file mode 100644 index 0000000..dfe077e --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.9778e-07) +mat.add_nuclide('U235', 7.4181e-05) +mat.add_nuclide('U236', 7.4088e-08) +mat.add_nuclide('U238', 6.6074e-04) +mat.add_nuclide('H1', 5.7216e-02) +mat.add_nuclide('N14', 2.8141e-03) +mat.add_element('O', 3.7850e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-29/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/geometry.xml new file mode 100644 index 0000000..fe614f7 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-29/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/materials.xml new file mode 100644 index 0000000..28241a5 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-29/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-29/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-33/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/generate_materials.py new file mode 100644 index 0000000..7c73f63 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.5579e-07) +mat.add_nuclide('U235', 6.8970e-05) +mat.add_nuclide('U236', 6.8884e-08) +mat.add_nuclide('U238', 6.1432e-04) +mat.add_nuclide('H1', 5.8085e-02) +mat.add_nuclide('N14', 2.6927e-03) +mat.add_element('O', 3.7826e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-33/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/geometry.xml new file mode 100644 index 0000000..39fb423 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-33/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/materials.xml new file mode 100644 index 0000000..f6949d8 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-33/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-33/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-34/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/generate_materials.py new file mode 100644 index 0000000..95fe3d3 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 5.2203e-07) +mat.add_nuclide('U235', 6.4780e-05) +mat.add_nuclide('U236', 6.4700e-08) +mat.add_nuclide('U238', 5.7701e-04) +mat.add_nuclide('H1', 5.8032e-02) +mat.add_nuclide('N14', 2.6337e-03) +mat.add_element('O', 3.7527e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-34/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/geometry.xml new file mode 100644 index 0000000..203d7e1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-34/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/materials.xml new file mode 100644 index 0000000..3f90c51 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-34/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-34/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-46/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/generate_materials.py new file mode 100644 index 0000000..5b7927e --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.9795e-07) +mat.add_nuclide('U235', 6.1792e-05) +mat.add_nuclide('U236', 6.1715e-08) +mat.add_nuclide('U238', 5.5039e-04) +mat.add_nuclide('H1', 5.8189e-02) +mat.add_nuclide('N14', 2.5925e-03) +mat.add_element('O', 3.7414e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-46/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/geometry.xml new file mode 100644 index 0000000..f68f2b5 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-46/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/materials.xml new file mode 100644 index 0000000..2f11cfb --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-46/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-46/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-51/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/generate_materials.py new file mode 100644 index 0000000..bd98715 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.8004e-07) +mat.add_nuclide('U235', 5.9569e-05) +mat.add_nuclide('U236', 5.9495e-08) +mat.add_nuclide('U238', 5.3059e-04) +mat.add_nuclide('H1', 5.8528e-02) +mat.add_nuclide('N14', 2.5544e-03) +mat.add_element('O', 3.7422e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-51/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/geometry.xml new file mode 100644 index 0000000..cbb77c7 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-51/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/materials.xml new file mode 100644 index 0000000..1279521 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-51/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-51/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-54/generate_materials.py b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/generate_materials.py new file mode 100644 index 0000000..41d678f --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 4.6378e-07) +mat.add_nuclide('U235', 5.7551e-05) +mat.add_nuclide('U236', 5.7480e-08) +mat.add_nuclide('U238', 5.1262e-04) +mat.add_nuclide('H1', 5.8561e-02) +mat.add_nuclide('N14', 2.5144e-03) +mat.add_element('O', 3.7278e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 4.3736e-05) +mat.add_element('Si', 1.0627e-03) +mat.add_element('Mn', 1.1561e-03) +mat.add_element('P', 1.3170e-05) +mat.add_element('S', 1.9782e-06) +mat.add_element('Ni', 8.3403e-03) +mat.add_element('Cr', 1.6775e-02) +mat.add_element('Fe', 5.9421e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-54/geometry.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/geometry.xml new file mode 100644 index 0000000..06b1559 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/geometry.xml @@ -0,0 +1,33 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-54/materials.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/materials.xml new file mode 100644 index 0000000..29ec2c1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-004/openmc/case-54/settings.xml b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-004/openmc/case-54/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-14.py b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-14.py new file mode 100644 index 0000000..951a9fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-14.py @@ -0,0 +1,89 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.9954e-05], + ['U238',0.00071216], + ['H1',0.056706999999999994], + ['N14',0.0029298285822], + ['N15',1.07714178e-05], + ['O16',0.038069566164], + ['O17',1.4433835999999999e-05]]) +# Material Name: Stainless Steel +m2 = mcdc.material(nuclides=[ + ['C0',4.373600000000001e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',4.3169999999999995e-05], + ['S32',2.83050331868e-06], + ['S33',2.2297485580000004e-08], + ['S34',1.2496497418e-07], + ['S36',4.3422156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.50710797e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.05452114434], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8873084392e-05], + ['N15',1.4291560800000001e-07], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-2.0, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=46.83, bc='interface') +s6 = mcdc.surface('plane-z', z=150.0, bc='interface') +s7 = mcdc.surface('plane-z', z=152.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s2 & +s6 & -s7, fill=m2) +c4 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c5 = mcdc.cell(-s1 & +s5 & -s6, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-30.py b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-30.py new file mode 100644 index 0000000..505bebd --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-30.py @@ -0,0 +1,89 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.4257e-05], + ['U238',0.00066142], + ['H1',0.057176000000000005], + ['N14',0.0028052864572000002], + ['N15',1.03135428e-05], + ['O16',0.037821660156], + ['O17',1.4339844e-05]]) +# Material Name: Stainless Steel +m2 = mcdc.material(nuclides=[ + ['C0',4.373600000000001e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',4.3169999999999995e-05], + ['S32',2.83050331868e-06], + ['S33',2.2297485580000004e-08], + ['S34',1.2496497418e-07], + ['S36',4.3422156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.50710797e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.05452114434], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8873084392e-05], + ['N15',1.4291560800000001e-07], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-2.0, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=54.2, bc='interface') +s6 = mcdc.surface('plane-z', z=150.0, bc='interface') +s7 = mcdc.surface('plane-z', z=152.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s2 & +s6 & -s7, fill=m2) +c4 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c5 = mcdc.cell(-s1 & +s5 & -s6, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-32.py b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-32.py new file mode 100644 index 0000000..bc6065a --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-32.py @@ -0,0 +1,89 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.897e-05], + ['U238',0.00061432], + ['H1',0.058085], + ['N14',0.0026828366399000003], + ['N15',9.8633601e-06], + ['O16',0.037811663945999996], + ['O17',1.4336053999999999e-05]]) +# Material Name: Stainless Steel +m2 = mcdc.material(nuclides=[ + ['C0',4.373600000000001e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',4.3169999999999995e-05], + ['S32',2.83050331868e-06], + ['S33',2.2297485580000004e-08], + ['S34',1.2496497418e-07], + ['S36',4.3422156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.50710797e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.05452114434], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8873084392e-05], + ['N15',1.4291560800000001e-07], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-2.0, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=63.55, bc='interface') +s6 = mcdc.surface('plane-z', z=150.0, bc='interface') +s7 = mcdc.surface('plane-z', z=152.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s2 & +s6 & -s7, fill=m2) +c4 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c5 = mcdc.cell(-s1 & +s5 & -s6, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-36.py b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-36.py new file mode 100644 index 0000000..8731b60 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-36.py @@ -0,0 +1,89 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.4857e-05], + ['U238',0.00057769], + ['H1',0.058115], + ['N14',0.0026195692404], + ['N15',9.6307596e-06], + ['O16',0.03754576476], + ['O17',1.4235240000000002e-05]]) +# Material Name: Stainless Steel +m2 = mcdc.material(nuclides=[ + ['C0',4.373600000000001e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',4.3169999999999995e-05], + ['S32',2.83050331868e-06], + ['S33',2.2297485580000004e-08], + ['S34',1.2496497418e-07], + ['S36',4.3422156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.50710797e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.05452114434], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8873084392e-05], + ['N15',1.4291560800000001e-07], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-2.0, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=83.55, bc='interface') +s6 = mcdc.surface('plane-z', z=150.0, bc='interface') +s7 = mcdc.surface('plane-z', z=152.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s2 & +s6 & -s7, fill=m2) +c4 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c5 = mcdc.cell(-s1 & +s5 & -s6, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-49.py b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-49.py new file mode 100644 index 0000000..3039f7b --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/mcdc/leu-sol-therm-007_case-49.py @@ -0,0 +1,89 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',6.1792e-05], + ['U238',0.00055039], + ['H1',0.058223], + ['N14',0.0025830036725], + ['N15',9.496327500000001e-06], + ['O16',0.037416813651], + ['O17',1.4186348999999999e-05]]) +# Material Name: Stainless Steel +m2 = mcdc.material(nuclides=[ + ['C0',4.373600000000001e-05], + ['Si28',0.00098012480936], + ['Si29',4.976794132e-05], + ['Si30',3.2807249319999995e-05], + ['Mn55',0.0011561], + ['P31',4.3169999999999995e-05], + ['S32',2.83050331868e-06], + ['S33',2.2297485580000004e-08], + ['S34',1.2496497418e-07], + ['S36',4.3422156e-10], + ['Ni58',0.0056778176907], + ['Ni60',0.0021870852093], + ['Ni61',9.50710797e-05], + ['Ni62',0.0003031282035], + ['Ni64',7.71978168e-05], + ['Cr50',0.0007288737500000001], + ['Cr52',0.014055604750000002], + ['Cr53',0.0015937927500000002], + ['Cr54',0.00039672875000000004], + ['Fe54',0.00347315745], + ['Fe56',0.05452114434], + ['Fe57',0.00125913099], + ['Fe58',0.00016756722000000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.8873084392e-05], + ['N15',1.4291560800000001e-07], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.5, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=29.8, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-2.0, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='interface') +s5 = mcdc.surface('plane-z', z=112.27, bc='interface') +s6 = mcdc.surface('plane-z', z=150.0, bc='interface') +s7 = mcdc.surface('plane-z', z=152.5, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s2 & +s3 & -s4, fill=m2) +c2 = mcdc.cell(+s1 & -s2 & +s4 & -s6, fill=m2) +c3 = mcdc.cell(-s2 & +s6 & -s7, fill=m2) +c4 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c5 = mcdc.cell(-s1 & +s5 & -s6, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-14/generate_materials.py b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/generate_materials.py new file mode 100644 index 0000000..28984cb --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +un = openmc.Material(name="Uranyl Nitrate Solution") +un.add_nuclide('U234', 6.4430e-07) +un.add_nuclide('U235', 7.9954e-05) +un.add_nuclide('U236', 7.9854e-08) +un.add_nuclide('U238', 7.1216e-04) +un.add_nuclide('H1', 5.6707e-02) +un.add_element('N', 2.9406e-03) +un.add_element('O', 3.8084e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +steel = openmc.Material(name="Stainless Steel") +steel.add_element('C', 4.3736e-05) +steel.add_element('Si', 1.0627e-03) +steel.add_element('Mn', 1.1561e-03) +steel.add_element('P', 4.3170e-05) +steel.add_element('S', 2.9782e-06) +steel.add_element('Ni', 8.3403e-03) +steel.add_element('Cr', 1.6775e-02) +steel.add_element('Fe', 5.9421e-02) + +air = openmc.Material(name="Air") +air.add_element('N', 3.9016e-05) +air.add_element('O', 1.0409e-05) + +materials = openmc.Materials([un, steel, air]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-14/geometry.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/geometry.xml new file mode 100644 index 0000000..3d5f8fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-14/materials.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/materials.xml new file mode 100644 index 0000000..7f69409 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-14/settings.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-14/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-30/generate_materials.py b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/generate_materials.py new file mode 100644 index 0000000..30608d1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +un = openmc.Material(name="Uranyl Nitrate Solution") +un.add_nuclide('U234', 5.9840e-07) +un.add_nuclide('U235', 7.4257e-05) +un.add_nuclide('U236', 7.4165e-08) +un.add_nuclide('U238', 6.6142e-04) +un.add_nuclide('H1', 5.7176e-02) +un.add_element('N', 2.8156e-03) +un.add_element('O', 3.7836e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +steel = openmc.Material(name="Stainless Steel") +steel.add_element('C', 4.3736e-05) +steel.add_element('Si', 1.0627e-03) +steel.add_element('Mn', 1.1561e-03) +steel.add_element('P', 4.3170e-05) +steel.add_element('S', 2.9782e-06) +steel.add_element('Ni', 8.3403e-03) +steel.add_element('Cr', 1.6775e-02) +steel.add_element('Fe', 5.9421e-02) + +air = openmc.Material(name="Air") +air.add_element('N', 3.9016e-05) +air.add_element('O', 1.0409e-05) + +materials = openmc.Materials([un, steel, air]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-30/geometry.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/geometry.xml new file mode 100644 index 0000000..ca953e7 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-30/materials.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/materials.xml new file mode 100644 index 0000000..5a0ce76 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-30/settings.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-30/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-32/generate_materials.py b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/generate_materials.py new file mode 100644 index 0000000..29f5ed9 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +un = openmc.Material(name="Uranyl Nitrate Solution") +un.add_nuclide('U234', 5.5579e-07) +un.add_nuclide('U235', 6.8970e-05) +un.add_nuclide('U236', 6.8884e-08) +un.add_nuclide('U238', 6.1432e-04) +un.add_nuclide('H1', 5.8085e-02) +un.add_element('N', 2.6927e-03) +un.add_element('O', 3.7826e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +steel = openmc.Material(name="Stainless Steel") +steel.add_element('C', 4.3736e-05) +steel.add_element('Si', 1.0627e-03) +steel.add_element('Mn', 1.1561e-03) +steel.add_element('P', 4.3170e-05) +steel.add_element('S', 2.9782e-06) +steel.add_element('Ni', 8.3403e-03) +steel.add_element('Cr', 1.6775e-02) +steel.add_element('Fe', 5.9421e-02) + +air = openmc.Material(name="Air") +air.add_element('N', 3.9016e-05) +air.add_element('O', 1.0409e-05) + +materials = openmc.Materials([un, steel, air]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-32/geometry.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/geometry.xml new file mode 100644 index 0000000..273b3cd --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-32/materials.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/materials.xml new file mode 100644 index 0000000..04a5ea5 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-32/settings.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-32/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-36/generate_materials.py b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/generate_materials.py new file mode 100644 index 0000000..f25f054 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +un = openmc.Material(name="Uranyl Nitrate Solution") +un.add_nuclide('U234', 5.2265e-07) +un.add_nuclide('U235', 6.4857e-05) +un.add_nuclide('U236', 6.4776e-08) +un.add_nuclide('U238', 5.7769e-04) +un.add_nuclide('H1', 5.8115e-02) +un.add_element('N', 2.6292e-03) +un.add_element('O', 3.7560e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +steel = openmc.Material(name="Stainless Steel") +steel.add_element('C', 4.3736e-05) +steel.add_element('Si', 1.0627e-03) +steel.add_element('Mn', 1.1561e-03) +steel.add_element('P', 4.3170e-05) +steel.add_element('S', 2.9782e-06) +steel.add_element('Ni', 8.3403e-03) +steel.add_element('Cr', 1.6775e-02) +steel.add_element('Fe', 5.9421e-02) + +air = openmc.Material(name="Air") +air.add_element('N', 3.9016e-05) +air.add_element('O', 1.0409e-05) + +materials = openmc.Materials([un, steel, air]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-36/geometry.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/geometry.xml new file mode 100644 index 0000000..4c92536 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-36/materials.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/materials.xml new file mode 100644 index 0000000..ab9925d --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-36/settings.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-36/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-49/generate_materials.py b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/generate_materials.py new file mode 100644 index 0000000..6957345 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +un = openmc.Material(name="Uranyl Nitrate Solution") +un.add_nuclide('U234', 4.9795e-07) +un.add_nuclide('U235', 6.1792e-05) +un.add_nuclide('U236', 6.1715e-08) +un.add_nuclide('U238', 5.5039e-04) +un.add_nuclide('H1', 5.8223e-02) +un.add_element('N', 2.5925e-03) +un.add_element('O', 3.7431e-02) +un.add_s_alpha_beta('c_H_in_H2O') + +steel = openmc.Material(name="Stainless Steel") +steel.add_element('C', 4.3736e-05) +steel.add_element('Si', 1.0627e-03) +steel.add_element('Mn', 1.1561e-03) +steel.add_element('P', 4.3170e-05) +steel.add_element('S', 2.9782e-06) +steel.add_element('Ni', 8.3403e-03) +steel.add_element('Cr', 1.6775e-02) +steel.add_element('Fe', 5.9421e-02) + +air = openmc.Material(name="Air") +air.add_element('N', 3.9016e-05) +air.add_element('O', 1.0409e-05) + +materials = openmc.Materials([un, steel, air]) +materials.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-49/geometry.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/geometry.xml new file mode 100644 index 0000000..3a3bed3 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-49/materials.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/materials.xml new file mode 100644 index 0000000..e97f6b8 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/materials.xml @@ -0,0 +1,49 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-007/openmc/case-49/settings.xml b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-007/openmc/case-49/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-105.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-105.py new file mode 100644 index 0000000..8e202b0 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-105.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00011858], + ['U238',0.0010562], + ['H1',0.05558199999999999], + ['N14',0.0028697], + ['O16',0.038466415701], + ['O17',1.4584299e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=40.09, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-113.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-113.py new file mode 100644 index 0000000..a484510 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-113.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.00010980999999999998], + ['U238',0.00097813], + ['H1',0.056459], + ['N14',0.0026597], + ['O16',0.038131542665999996], + ['O17',1.4457333999999998e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=42.77, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-125.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-125.py new file mode 100644 index 0000000..2b5e38b --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-125.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',9.4999e-05], + ['U238',0.0008461700000000001], + ['H1',0.0578], + ['N14',0.0023658], + ['O16',0.037626734061], + ['O17',1.4265938999999998e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=51.37, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-129.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-129.py new file mode 100644 index 0000000..34ed2b6 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-129.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',8.9609e-05], + ['U238',0.00079816], + ['H1',0.058265], + ['N14',0.0022589], + ['O16',0.037430808345], + ['O17',1.4191654999999999e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=56.96, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-131.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-131.py new file mode 100644 index 0000000..148e77f --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-131.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',8.4015e-05], + ['U238',0.00074833], + ['H1',0.058738], + ['N14',0.002148], + ['O16',0.037223886798], + ['O17',1.4113202e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=66.39, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-140.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-140.py new file mode 100644 index 0000000..a627c86 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-140.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.9545e-05], + ['U238',0.00070852], + ['H1',0.058778], + ['N14',0.0021527], + ['O16',0.037122925077000005], + ['O17',1.4074923000000001e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=81.47, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-196.py b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-196.py new file mode 100644 index 0000000..9c2b41d --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/mcdc/leu-sol-therm-016_case-196.py @@ -0,0 +1,114 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Uranyl Nitrate Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',7.6531e-05], + ['U238',0.00068167], + ['H1',0.059066], + ['N14',0.0020989], + ['O16',0.037042955397], + ['O17',1.4044603000000001e-05]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['C0',7.1567e-05], + ['Si28',0.0065865825972], + ['Si29',0.00033444787140000004], + ['Si30',0.00022046953140000003], + ['Mn55',0.0099095], + ['P31',5.0879e-05], + ['S32',9.9070467376e-07], + ['S33',7.80434456e-09], + ['S34',4.373899976e-08], + ['S36',1.5198192e-10], + ['Ni58',0.00582738264], + ['Ni60',0.00224469736], + ['Ni61',9.757543999999999e-05], + ['Ni62',0.00031111320000000003], + ['Ni64',7.923136e-05], + ['Cr50',0.00072670125], + ['Cr52',0.01401371025], + ['Cr53',0.00158904225], + ['Cr54',0.00039554625], + ['Fe54',0.003481282], + ['Fe56',0.05464868240000001], + ['Fe57',0.0012620764000000001], + ['Fe58',0.0001679592]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066658], + ['O16',0.033316368309], + ['O17',1.2631690999999998e-05]]) +# Material Name: Air +m4 = mcdc.material(nuclides=[ + ['N14',3.9016e-05], + ['O16',1.0405054989e-05], + ['O17',3.945011e-09]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-67.045, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-37.045, bc='interface') +s3 = mcdc.surface('plane-x', x=-34.515, bc='interface') +s4 = mcdc.surface('plane-x', x=34.515, bc='interface') +s5 = mcdc.surface('plane-x', x=37.045, bc='interface') +s6 = mcdc.surface('plane-x', x=67.045, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-46.57, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-16.57, bc='interface') +s13 = mcdc.surface('plane-y', y=-14.04, bc='interface') +s14 = mcdc.surface('plane-y', y=14.04, bc='interface') +s15 = mcdc.surface('plane-y', y=16.57, bc='interface') +s16 = mcdc.surface('plane-y', y=46.57, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-32.04, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-2.04, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=102.34, bc='interface') +s25 = mcdc.surface('plane-z', z=149.75, bc='interface') +s26 = mcdc.surface('plane-z', z=152.63, bc='interface') +s27 = mcdc.surface('plane-z', z=172.63, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s21 & -s22, fill=m3) +c2 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s22 & -s23, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s23 & -s24, fill=m1) +c4 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s24 & -s25, fill=m4) +c5 = mcdc.cell(+s3 & -s4 & +s13 & -s14 & +s25 & -s26, fill=m2) +c6 = mcdc.cell(+s2 & -s3 & +s12 & -s15 & +s22 & -s26, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s12 & -s13 & +s22 & -s26, fill=m2) +c8 = mcdc.cell(+s3 & -s4 & +s14 & -s15 & +s22 & -s26, fill=m2) +c9 = mcdc.cell(+s4 & -s5 & +s12 & -s15 & +s22 & -s26, fill=m2) +c10 = mcdc.cell(+s1 & -s2 & +s11 & -s16 & +s22 & -s26, fill=m3) +c11 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s22 & -s26, fill=m3) +c12 = mcdc.cell(+s2 & -s5 & +s15 & -s16 & +s22 & -s26, fill=m3) +c13 = mcdc.cell(+s5 & -s6 & +s11 & -s16 & +s22 & -s26, fill=m3) +c14 = mcdc.cell(+s1 & -s6 & +s11 & -s16 & +s26 & -s27, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-105/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/generate_materials.py new file mode 100644 index 0000000..51a577c --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 9.5555e-07) +mat.add_nuclide('U235', 1.1858e-04) +mat.add_nuclide('U236', 1.1843e-07) +mat.add_nuclide('U238', 1.0562e-03) +mat.add_nuclide('H1', 5.5582e-02) +mat.add_nuclide('N14', 2.8697e-03) +mat.add_element('O', 3.8481e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-105/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/geometry.xml new file mode 100644 index 0000000..f827ed1 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-105/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/materials.xml new file mode 100644 index 0000000..0f42ecc --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-105/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-105/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-113/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/generate_materials.py new file mode 100644 index 0000000..8c05fc9 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 8.8494e-07) +mat.add_nuclide('U235', 1.0981e-04) +mat.add_nuclide('U236', 1.0968e-07) +mat.add_nuclide('U238', 9.7813e-04) +mat.add_nuclide('H1', 5.6459e-02) +mat.add_nuclide('N14', 2.6597e-03) +mat.add_element('O', 3.8146e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-113/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/geometry.xml new file mode 100644 index 0000000..658b195 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-113/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/materials.xml new file mode 100644 index 0000000..bcad54a --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-113/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-113/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-125/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/generate_materials.py new file mode 100644 index 0000000..69a27de --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 7.6555e-07) +mat.add_nuclide('U235', 9.4999e-05) +mat.add_nuclide('U236', 9.4881e-08) +mat.add_nuclide('U238', 8.4617e-04) +mat.add_nuclide('H1', 5.7800e-02) +mat.add_nuclide('N14', 2.3658e-03) +mat.add_element('O', 3.7641e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-125/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/geometry.xml new file mode 100644 index 0000000..4f60e4e --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-125/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/materials.xml new file mode 100644 index 0000000..6abf431 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-125/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-125/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-129/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/generate_materials.py new file mode 100644 index 0000000..3342c0a --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 7.2211e-07) +mat.add_nuclide('U235', 8.9609e-05) +mat.add_nuclide('U236', 8.9498e-08) +mat.add_nuclide('U238', 7.9816e-04) +mat.add_nuclide('H1', 5.8265e-02) +mat.add_nuclide('N14', 2.2589e-03) +mat.add_element('O', 3.7445e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-129/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/geometry.xml new file mode 100644 index 0000000..6f453ef --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-129/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/materials.xml new file mode 100644 index 0000000..958df8d --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-129/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-129/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-131/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/generate_materials.py new file mode 100644 index 0000000..df9107d --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.7703e-07) +mat.add_nuclide('U235', 8.4015e-05) +mat.add_nuclide('U236', 8.3910e-08) +mat.add_nuclide('U238', 7.4833e-04) +mat.add_nuclide('H1', 5.8738e-02) +mat.add_nuclide('N14', 2.1480e-03) +mat.add_element('O', 3.7238e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-131/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/geometry.xml new file mode 100644 index 0000000..da4c348 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-131/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/materials.xml new file mode 100644 index 0000000..56685a3 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-131/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-131/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-140/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/generate_materials.py new file mode 100644 index 0000000..7b6048b --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.4101e-07) +mat.add_nuclide('U235', 7.9545e-05) +mat.add_nuclide('U236', 7.9446e-08) +mat.add_nuclide('U238', 7.0852e-04) +mat.add_nuclide('H1', 5.8778e-02) +mat.add_nuclide('N14', 2.1527e-03) +mat.add_element('O', 3.7137e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-140/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/geometry.xml new file mode 100644 index 0000000..6ba7d63 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-140/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/materials.xml new file mode 100644 index 0000000..c87ab15 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-140/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-140/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-196/generate_materials.py b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/generate_materials.py new file mode 100644 index 0000000..a9a34e0 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Uranyl Nitrate Solution" +mat.set_density('sum') +mat.add_nuclide('U234', 6.1672e-07) +mat.add_nuclide('U235', 7.6531e-05) +mat.add_nuclide('U236', 7.6435e-08) +mat.add_nuclide('U238', 6.8167e-04) +mat.add_nuclide('H1', 5.9066e-02) +mat.add_nuclide('N14', 2.0989e-03) +mat.add_element('O', 3.7057e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('C', 7.1567e-05) +mat.add_element('Si', 7.1415e-03) +mat.add_element('Mn', 9.9095e-03) +mat.add_element('P', 5.0879e-05) +mat.add_element('S', 1.0424e-06) +mat.add_element('Ni', 8.5600e-03) +mat.add_element('Cr', 1.6725e-02) +mat.add_element('Fe', 5.9560e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6658e-02) +mat.add_element('O', 3.3329e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('N14', 3.9016e-05) +mat.add_element('O', 1.0409e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-196/geometry.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/geometry.xml new file mode 100644 index 0000000..c284219 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/geometry.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-196/materials.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/materials.xml new file mode 100644 index 0000000..7a0109d --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/materials.xml @@ -0,0 +1,54 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/leu-sol-therm-016/openmc/case-196/settings.xml b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/settings.xml new file mode 100644 index 0000000..786cd19 --- /dev/null +++ b/icsbep/openmc/leu-sol-therm-016/openmc/case-196/settings.xml @@ -0,0 +1,17 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + 0. 0. 0. + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-fast-001/mcdc/mix-comp-fast-001.py b/icsbep/openmc/mix-comp-fast-001/mcdc/mix-comp-fast-001.py new file mode 100644 index 0000000..66929e5 --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-001/mcdc/mix-comp-fast-001.py @@ -0,0 +1,361 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Inner Core 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu240',0.000117624], + ['U235',1.26065e-05], + ['U238',0.0057929], + ['Pu239',0.0008865280000000001], + ['Pu238',3.33696e-07], + ['Pu242',1.40289e-06], + ['Am241',2.95925e-06], + ['Cr50',0.00011702996800000003], + ['Cr52',0.0022568064416], + ['Cr53',0.0002559037344], + ['Cr54',6.369985600000001e-05], + ['Ni58',0.00081551360817], + ['Ni60',0.00031413438183], + ['Ni61',1.3655204069999999e-05], + ['Ni62',4.3538765850000004e-05], + ['Ni64',1.1088040080000001e-05], + ['Fe54',0.0007517312950000002], + ['Fe56',0.011800573694], + ['Fe57',0.000272526709], + ['Fe58',3.6268302e-05], + ['Al27',4.02385e-06], + ['Na23',0.00927752], + ['O16',0.0137473877646], + ['O17',5.2122354e-06], + ['C0',3.66446e-05], + ['Mo100',2.300158896e-05], + ['Mo92',3.458028291e-05], + ['Mo94',2.1686740329999997e-05], + ['Mo95',3.746964507e-05], + ['Mo96',3.935811707e-05], + ['Mo97',2.261917338e-05], + ['Mo98',5.734345228e-05], + ['Mn55',0.000225651], + ['Cu63',1.706545935e-05], + ['Cu65',7.61344065e-06], + ['Si28',0.00014975702060319998], + ['Si29',7.6042342184e-06], + ['Si30',5.012745178399999e-06], + ['Cl35',2.2608944126999995e-07], + ['Cl37',7.232055873e-08], + ['Co59',8.32631e-07]]) +# Material Name: Outer Core 1 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu240',0.00011775099999999999], + ['U235',1.2660000000000002e-05], + ['U238',0.00581701], + ['Pu239',0.000887794], + ['Pu238',4.7005600000000006e-07], + ['Pu242',1.76624e-06], + ['Am241',2.40381e-06], + ['Cr50',0.00011684791249999999], + ['Cr52',0.0022532956825], + ['Cr53',0.0002555056425], + ['Cr54',6.36007625e-05], + ['Ni58',0.0008093390333399999], + ['Ni60',0.00031175594666], + ['Ni61',1.3551815139999998e-05], + ['Ni62',4.32091167e-05], + ['Ni64',1.100408816e-05], + ['Fe54',0.00077442743], + ['Fe56',0.012156854476], + ['Fe57',0.000280754786], + ['Fe58',3.7363308e-05], + ['Al27',3.6239e-06], + ['Na23',0.00912725], + ['O16',0.0142657912152], + ['O17',5.4087848e-06], + ['C0',3.40434e-05], + ['Mo100',2.329566288e-05], + ['Mo92',3.502238973e-05], + ['Mo94',2.196400399e-05], + ['Mo95',3.794869221e-05], + ['Mo96',3.986130821e-05], + ['Mo97',2.2908358140000002e-05], + ['Mo98',5.807658484000001e-05], + ['Mn55',0.000224037], + ['Cu63',1.717195035e-05], + ['Cu65',7.660949650000001e-06], + ['Si28',0.000142905277676], + ['Si29',7.256322261999999e-06], + ['Si30',4.783400062e-06], + ['Cl35',2.2513935193199998e-07], + ['Cl37',7.2016648068e-08], + ['Co59',1.69138e-07]]) +# Material Name: Inner Axial reflector 1 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',8.29314e-05], + ['U238',0.0371138], + ['Cr50',7.15365145e-05], + ['Cr52',0.0013795104749], + ['Cr53',0.0001564254141], + ['Cr54',3.8937596500000005e-05], + ['Ni58',0.000469304448606], + ['Ni60',0.000180775233394], + ['Ni61',7.858174225999999e-06], + ['Ni62',2.5055298030000005e-05], + ['Ni64',6.380845744000001e-06], + ['Fe54',0.0003542216125], + ['Fe56',0.005560521785], + ['Fe57',0.0001284166975], + ['Fe58',1.7089905e-05], + ['C0',3.67281e-05], + ['Mo100',1.03486152e-06], + ['Mo92',1.555797045e-06], + ['Mo94',9.757053349999998e-07], + ['Mo95',1.685791965e-06], + ['Mo96',1.770755965e-06], + ['Mo97',1.01765631e-06], + ['Mo98',2.57993186e-06], + ['Mn55',0.000143193], + ['Cu63',1.365138555e-05], + ['Cu65',6.0903144500000005e-06], + ['Si28',9.79737444704e-05], + ['Si29',4.9748272048e-06], + ['Si30',3.2794283248e-06]]) +# Material Name: Outer Axial Reflector 1 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',8.27657e-05], + ['U238',0.0370414], + ['Cr50',7.191235700000001e-05], + ['Cr52',0.0013867582234000002], + ['Cr53',0.00015724725060000001], + ['Cr54',3.9142169e-05], + ['Ni58',0.00047166195165299996], + ['Ni60',0.000181683339347], + ['Ni61',7.897648963e-06], + ['Ni62',2.5181160765e-05], + ['Ni64',6.412899272e-06], + ['Fe54',0.0003558523675], + ['Fe56',0.005586121151], + ['Fe57',0.0001290078985], + ['Fe58',1.7168583e-05], + ['C0',3.66405e-05], + ['Mo100',1.04002584e-06], + ['Mo92',1.563561015e-06], + ['Mo94',9.80574445e-07], + ['Mo95',1.694204655e-06], + ['Mo96',1.779592655e-06], + ['Mo97',1.02273477e-06], + ['Mo98',2.59280662e-06], + ['Mn55',0.000143788], + ['Cu63',1.3704147e-05], + ['Cu65',6.113852999999999e-06], + ['Si28',9.784370062160001e-05], + ['Si29',4.9682239492e-06], + ['Si30',3.2750754292e-06]]) +# Material Name: Inner Axial reflector 2 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',8.65264e-05], + ['U238',0.0387479], + ['Cr50',6.2989465e-05], + ['Cr52',0.001214689133], + ['Cr53',0.000137735997], + ['Cr54',3.4285405e-05], + ['Ni58',0.00041357805980399997], + ['Ni60',0.000159309528196], + ['Ni61',6.925074884e-06], + ['Ni62',2.208016902e-05], + ['Ni64',5.623168096e-06], + ['Fe54',0.00030717228500000003], + ['Fe56',0.0048219479620000005], + ['Fe57',0.000111359807], + ['Fe58',1.4819946e-05], + ['C0',2.71677e-05], + ['Mo100',9.784535040000001e-07], + ['Mo92',1.4709939840000002e-06], + ['Mo94',9.225217919999999e-07], + ['Mo95',1.593903168e-06], + ['Mo96',1.674235968e-06], + ['Mo97',9.62186112e-07], + ['Mo98',2.439305472e-06], + ['Mn55',0.000127167], + ['Cu63',1.3185452850000002e-05], + ['Cu65',5.882447149999999e-06], + ['Si28',8.780551448008e-05], + ['Si29',4.45851349796e-06], + ['Si30',2.9390720219599996e-06]]) +# Material Name: Outer Axial Reflector 2 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',8.55655e-05], + ['U238',0.0383153], + ['Cr50',6.37937245e-05], + ['Cr52',0.0012301984769], + ['Cr53',0.0001394946321], + ['Cr54',3.47231665e-05], + ['Ni58',0.00041871786575400005], + ['Ni60',0.000161289372246], + ['Ni61',7.011137334000001e-06], + ['Ni62',2.2354573770000004e-05], + ['Ni64',5.693050896e-06], + ['Fe54',0.00031093412700000005], + ['Fe56',0.0048810008364], + ['Fe57',0.00011272359540000001], + ['Fe58',1.50014412e-05], + ['C0',2.73042e-05], + ['Mo100',9.94336224e-07], + ['Mo92',1.4948718540000005e-06], + ['Mo94',9.374966020000001e-07], + ['Mo95',1.6197761580000003e-06], + ['Mo96',1.7014129580000001e-06], + ['Mo97',9.778047720000001e-07], + ['Mo98',2.4789014320000002e-06], + ['Mn55',0.000128523], + ['Cu63',1.328668845e-05], + ['Cu65',5.9276115499999996e-06], + ['Si28',8.804540387776001e-05], + ['Si29',4.47069439712e-06], + ['Si30',2.9471017251200004e-06]]) +# Material Name: Radial Reflector 1 +# Depletable +m8 = mcdc.material(nuclides=[ + ['U235',8.66555e-05], + ['U238',0.0388076], + ['Cr50',5.1193224500000014e-05], + ['Cr52',0.0009872103769], + ['Cr53',0.0001119417321], + ['Cr54',2.7864666500000003e-05], + ['Ni58',0.00032389627482], + ['Ni60',0.00012476426518], + ['Ni61',5.42341622e-06], + ['Ni62',1.72922241e-05], + ['Ni64',4.40381968e-06], + ['Fe54',0.000247826831], + ['Fe56',0.0038903512492], + ['Fe57',8.98451762e-05], + ['Fe58',1.1956743599999999e-05], + ['C0',1.85721e-05], + ['Mo100',7.971917184000001e-07], + ['Mo92',1.1984874264e-06], + ['Mo94',7.516215432e-07], + ['Mo95',1.2986272728000002e-06], + ['Mo96',1.3640781528e-06], + ['Mo97',7.839379152e-07], + ['Mo98',1.9874159712e-06], + ['Mn55',0.000104936], + ['Cu63',1.1807224200000002e-05], + ['Cu65',5.2675758000000005e-06], + ['Si28',6.242547444864e-05], + ['Si29',3.16978747968e-06], + ['Si30',2.08953807168e-06]]) +# Material Name: Radial Reflector 2 +m9 = mcdc.material(nuclides=[ + ['Cr50',5.178501350000001e-05], + ['Cr52',0.0009986224387000002], + ['Cr53',0.0001132357683], + ['Cr54',2.8186779500000003e-05], + ['Ni58',0.00032820894643499995], + ['Ni60',0.000126425498565], + ['Ni61',5.495628884999999e-06], + ['Ni62',1.7522469675e-05], + ['Ni64',4.46245644e-06], + ['Fe54',0.0002519329435], + ['Fe56',0.0039548084342], + ['Fe57',9.13337737e-05], + ['Fe58',1.2154848600000002e-05], + ['C0',1.98501e-05], + ['Mo100',8.065576512e-07], + ['Mo92',1.2125680452000002e-06], + ['Mo94',7.604520875999999e-07], + ['Mo95',1.3138844004e-06], + ['Mo96',1.3801042404e-06], + ['Mo97',7.931481336e-07], + ['Mo98',2.0107654416000002e-06], + ['Mn55',0.00010605800000000002], + ['Cu63',1.1888337150000001e-05], + ['Cu65',5.3037628500000005e-06], + ['Si28',6.351821169728e-05], + ['Si29',3.2252735593599993e-06], + ['Si30',2.1261147433599997e-06]]) +# Material Name: Empty Matrix +m10 = mcdc.material(nuclides=[ + ['Cr50',5.178501350000001e-05], + ['Cr52',0.0009986224387000002], + ['Cr53',0.0001132357683], + ['Cr54',2.8186779500000003e-05], + ['Ni58',0.00032820894643499995], + ['Ni60',0.000126425498565], + ['Ni61',5.495628884999999e-06], + ['Ni62',1.7522469675e-05], + ['Ni64',4.46245644e-06], + ['Fe54',0.0002519329435], + ['Fe56',0.0039548084342], + ['Fe57',9.13337737e-05], + ['Fe58',1.2154848600000002e-05], + ['C0',1.98501e-05], + ['Mo100',8.065576512e-07], + ['Mo92',1.2125680452000002e-06], + ['Mo94',7.604520875999999e-07], + ['Mo95',1.3138844004e-06], + ['Mo96',1.3801042404e-06], + ['Mo97',7.931481336e-07], + ['Mo98',2.0107654416000002e-06], + ['Mn55',0.00010605800000000002], + ['Cu63',1.1888337150000001e-05], + ['Cu65',5.3037628500000005e-06], + ['Si28',6.351821169728e-05], + ['Si29',3.2252735593599993e-06], + ['Si30',2.1261147433599997e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=24.3435, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=80.6781, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=112.2504, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=140.2589, bc='vacuum') +s5 = mcdc.surface('plane-z', z=0.0, bc='reflective') +s6 = mcdc.surface('plane-z', z=76.2813, bc='interface') +s7 = mcdc.surface('plane-z', z=101.7257, bc='interface') +s8 = mcdc.surface('plane-z', z=106.68, bc='interface') +s9 = mcdc.surface('plane-z', z=110.5357, bc='interface') +s10 = mcdc.surface('plane-z', z=121.92, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & +s5 & -s6, fill=m1) +c2 = mcdc.cell(+s1 & -s2 & +s5 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s6 & -s7, fill=m4) +c4 = mcdc.cell(+s1 & -s2 & +s6 & -s7, fill=m5) +c5 = mcdc.cell(-s1 & +s7 & -s9, fill=m6) +c6 = mcdc.cell(+s1 & -s2 & +s7 & -s9, fill=m7) +c7 = mcdc.cell(+s2 & -s3 & +s5 & -s8, fill=m8) +c8 = mcdc.cell(+s2 & -s3 & +s8 & -s9, fill=m9) +c9 = mcdc.cell(-s3 & +s9 & -s10, fill=m10) +c10 = mcdc.cell(+s3 & -s4 & +s5 & -s10, fill=m10) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-141.0,141.0], y=[-141.0,141.0], z=[0.0,122.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-comp-fast-001/openmc/generate_materials.py b/icsbep/openmc/mix-comp-fast-001/openmc/generate_materials.py new file mode 100644 index 0000000..c58e82d --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-001/openmc/generate_materials.py @@ -0,0 +1,158 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Inner Core 1" +mat.set_density('sum') +mat.add_nuclide('Pu240', 1.17624E-04) +mat.add_nuclide('Pu241', 1.33836E-05) +mat.add_nuclide('U235', 1.26065E-05) +mat.add_nuclide('U238', 5.79290E-03) +mat.add_nuclide('Pu239', 8.86528E-04) +mat.add_nuclide('Pu238', 3.33696E-07) +mat.add_nuclide('Pu242', 1.40289E-06) +mat.add_nuclide('Am241', 2.95925E-06) +mat.add_element('Cr', 2.69344E-03) +mat.add_element('Ni', 1.19793E-03) +mat.add_element('Fe', 1.28611E-02) +mat.add_element('Al', 4.02385E-06) +mat.add_element('Na', 9.27752E-03) +mat.add_element('O', 1.37526E-02) +mat.add_element('C', 3.66446E-05) +mat.add_element('Mo', 2.36059E-04) +mat.add_element('Mn', 2.25651E-04) +mat.add_element('Cu', 2.46789E-05) +mat.add_element('Si', 1.62374E-04) +mat.add_element('Cl', 2.98410E-07) +mat.add_element('Co', 8.32631E-07) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Outer Core 1" +mat.set_density('sum') +mat.add_nuclide('Pu240', 1.17751E-04) +mat.add_nuclide('Pu241', 1.52377E-05) +mat.add_nuclide('U235', 1.26600E-05) +mat.add_nuclide('U238', 5.81701E-03) +mat.add_nuclide('Pu239', 8.87794E-04) +mat.add_nuclide('Pu238', 4.70056E-07) +mat.add_nuclide('Pu242', 1.76624E-06) +mat.add_nuclide('Am241', 2.40381E-06) +mat.add_element('Cr', 2.68925E-03) +mat.add_element('Ni', 1.18886E-03) +mat.add_element('Fe', 1.32494E-02) +mat.add_element('Al', 3.62390E-06) +mat.add_element('Na', 9.12725E-03) +mat.add_element('O', 1.42712E-02) +mat.add_element('C', 3.40434E-05) +mat.add_element('Mo', 2.39077E-04) +mat.add_element('Mn', 2.24037E-04) +mat.add_element('Cu', 2.48329E-05) +mat.add_element('Si', 1.54945E-04) +mat.add_element('Cl', 2.97156E-07) +mat.add_element('Co', 1.69138E-07) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Inner Axial reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.29314E-05) +mat.add_nuclide('U238', 3.71138E-02) +mat.add_element('Cr', 1.64641E-03) +mat.add_element('Ni', 6.89374E-04) +mat.add_element('Fe', 6.06025E-03) +mat.add_element('C', 3.67281E-05) +mat.add_element('Mo', 1.06205E-05) +mat.add_element('Mn', 1.43193E-04) +mat.add_element('Cu', 1.97417E-05) +mat.add_element('Si', 1.06228E-04) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Inner Axial reflector 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.65264E-05) +mat.add_nuclide('U238', 3.87479E-02) +mat.add_element('Cr', 1.44970E-03) +mat.add_element('Ni', 6.07516E-04) +mat.add_element('Fe', 5.25530E-03) +mat.add_element('C', 2.71677E-05) +mat.add_element('Mo', 1.00416E-05) +mat.add_element('Mn', 1.27167E-04) +mat.add_element('Cu', 1.90679E-05) +mat.add_element('Si', 9.52031E-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Outer Axial Reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.27657E-05) +mat.add_nuclide('U238', 3.70414E-02) +mat.add_element('Cr', 1.65506E-03) +mat.add_element('Ni', 6.92837E-04) +mat.add_element('Fe', 6.08815E-03) +mat.add_element('C', 3.66405E-05) +mat.add_element('Mo', 1.06735E-05) +mat.add_element('Mn', 1.43788E-04) +mat.add_element('Cu', 1.98180E-05) +mat.add_element('Si', 1.06087E-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Outer Axial Reflector 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.55655E-05) +mat.add_nuclide('U238', 3.83153E-02) +mat.add_element('Cr', 1.46821E-03) +mat.add_element('Ni', 6.15066E-04) +mat.add_element('Fe', 5.31966E-03) +mat.add_element('C', 2.73042E-05) +mat.add_element('Mo', 1.02046E-05) +mat.add_element('Mn', 1.28523E-04) +mat.add_element('Cu', 1.92143E-05) +mat.add_element('Si', 9.54632E-05) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Radial Reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.66555E-05) +mat.add_nuclide('U238', 3.88076E-02) +mat.add_element('Cr', 1.17821E-03) +mat.add_element('Ni', 4.75780E-04) +mat.add_element('Fe', 4.23998E-03) +mat.add_element('C', 1.85721E-05) +mat.add_element('Mo', 8.18136E-06) +mat.add_element('Mn', 1.04936E-04) +mat.add_element('Cu', 1.70748E-05) +mat.add_element('Si', 6.76848E-05) +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "Radial Reflector 2" +mat.set_density('sum') +mat.add_element('Cr', 1.19183E-03) +mat.add_element('Ni', 4.82115E-04) +mat.add_element('Fe', 4.31023E-03) +mat.add_element('C', 1.98501E-05) +mat.add_element('Mo', 8.27748E-06) +mat.add_element('Mn', 1.06058E-04) +mat.add_element('Cu', 1.71921E-05) +mat.add_element('Si', 6.88696E-05) +mats.append(mat) + +mat = openmc.Material(10) +mat.name = "Empty Matrix" +mat.set_density('sum') +mat.add_element('Cr', 1.19183E-03) +mat.add_element('Ni', 4.82115E-04) +mat.add_element('Fe', 4.31023E-03) +mat.add_element('C', 1.98501E-05) +mat.add_element('Mo', 8.27748E-06) +mat.add_element('Mn', 1.06058E-04) +mat.add_element('Cu', 1.71921E-05) +mat.add_element('Si', 6.88696E-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-fast-001/openmc/geometry.xml b/icsbep/openmc/mix-comp-fast-001/openmc/geometry.xml new file mode 100644 index 0000000..2b157a4 --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-001/openmc/geometry.xml @@ -0,0 +1,52 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-fast-001/openmc/materials.xml b/icsbep/openmc/mix-comp-fast-001/openmc/materials.xml new file mode 100644 index 0000000..8d9cccb --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-001/openmc/materials.xml @@ -0,0 +1,313 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-fast-001/openmc/settings.xml b/icsbep/openmc/mix-comp-fast-001/openmc/settings.xml new file mode 100644 index 0000000..591e8be --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -141. -141. 0. 141. 141. 122. + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-fast-002/mcdc/mix-comp-fast-002.py b/icsbep/openmc/mix-comp-fast-002/mcdc/mix-comp-fast-002.py new file mode 100644 index 0000000..f417f46 --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-002/mcdc/mix-comp-fast-002.py @@ -0,0 +1,425 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Inner Core 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu240',0.00032178], + ['U235',1.1872e-05], + ['U238',0.005562], + ['Pu239',0.0008384399999999999], + ['Pu238',1.1083e-06], + ['Pu242',1.7447e-05], + ['Am241',1.4681e-05], + ['Cr50',0.00011641124000000001], + ['Cr52',0.002244874888], + ['Cr53',0.000254550792], + ['Cr54',6.336308e-05], + ['Ni58',0.0008106597252], + ['Ni60',0.00031226467480000003], + ['Ni61',1.3573929199999998e-05], + ['Ni62',4.327962600000001e-05], + ['Ni64',1.1022044800000002e-05], + ['Fe54',0.0007484522499999999], + ['Fe56',0.011749099700000001], + ['Fe57',0.00027133795], + ['Fe58',3.61101e-05], + ['Al27',4.1057e-06], + ['Na23',0.0091676], + ['O16',0.013678813764], + ['O17',5.186236e-06], + ['C0',3.6621e-05], + ['Mo100',2.30562528e-05], + ['Mo92',3.46624638e-05], + ['Mo94',2.1738279399999997e-05], + ['Mo95',3.7558692600000005e-05], + ['Mo96',3.94516526e-05], + ['Mo97',2.26729284e-05], + ['Mo98',5.747973039999999e-05], + ['Mn55',0.00022447], + ['Cu63',1.6997069999999998e-05], + ['Cu65',7.5829299999999986e-06], + ['Si28',0.000149246068176], + ['Si29',7.578289512e-06], + ['Si30',4.995642311999999e-06], + ['Ca40',2.040026404e-06], + ['Ca42',1.3615468000000003e-08], + ['Ca43',2.8409400000000003e-09], + ['Ca44',4.3897784000000004e-08], + ['Ca46',8.417600000000002e-11], + ['Ca48',3.935228e-09], + ['Cl35',2.2338464148e-07], + ['Cl37',7.145535852e-08], + ['Co59',8.2889e-07]]) +# Material Name: Outer Core 1 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu240',0.00011749], + ['U235',1.2575e-05], + ['U238',0.005782], + ['Pu239',0.00088583], + ['Pu238',4.6444e-07], + ['Pu242',1.762e-06], + ['Am241',2.9643000000000006e-06], + ['Cr50',0.000116919605], + ['Cr52',0.002254678201], + ['Cr53',0.00025566240899999997], + ['Cr54',6.3639785e-05], + ['Ni58',0.0008090939565000001], + ['Ni60',0.0003116615435], + ['Ni61',1.35477115e-05], + ['Ni62',4.3196032500000003e-05], + ['Ni64',1.1000756000000001e-05], + ['Fe54',0.0007732934999999999], + ['Fe56',0.0121390542], + ['Fe57',0.00028034370000000003], + ['Fe58',3.7308600000000004e-05], + ['Al27',1.8593e-05], + ['Na23',0.0090718], + ['O16',0.014186621232], + ['O17',5.378768e-06], + ['C0',3.3605e-05], + ['Mo100',2.32638e-05], + ['Mo92',3.4974487500000005e-05], + ['Mo94',2.1933962499999998e-05], + ['Mo95',3.78967875e-05], + ['Mo96',3.9806787499999996e-05], + ['Mo97',2.2877025e-05], + ['Mo98',5.799715e-05], + ['Mn55',0.00022395], + ['Cu63',1.7205903e-05], + ['Cu65',7.676097e-06], + ['Si28',0.000141821578936], + ['Si29',7.2012951320000005e-06], + ['Si30',4.747125932e-06], + ['Ca40',2.0190871480000003e-06], + ['Ca42',1.3475716000000001e-08], + ['Ca43',2.8117800000000004e-09], + ['Ca44',4.3447208000000005e-08], + ['Ca46',8.331200000000001e-11], + ['Ca48',3.894836e-09], + ['Cl35',2.2385438261999998e-07], + ['Cl37',7.160561738e-08], + ['Co59',5.4094999999999996e-08]]) +# Material Name: Pu-Al ring +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu240',5.0694000000000006e-05], + ['U235',1.2151e-05], + ['U238',0.0057042], + ['Pu239',0.0010697], + ['Pu238',1.6247999999999998e-09], + ['Pu242',1.1005e-07], + ['Am241',1.9758e-06], + ['Cr50',0.00011396934999999999], + ['Cr52',0.00219778547], + ['Cr53',0.00024921123], + ['Cr54',6.203395e-05], + ['Ni58',0.0007929597311999998], + ['Ni60',0.0003054466688], + ['Ni61',1.3277555199999998e-05], + ['Ni62',4.2334656e-05], + ['Ni64',1.07813888e-05], + ['Fe54',0.000769202], + ['Fe56',0.0120748264], + ['Fe57',0.0002788604], + ['Fe58',3.71112e-05], + ['Al27',0.00011477], + ['Na23',0.009342], + ['O16',0.014380547705999997], + ['O17',5.452294e-06], + ['C0',4.0021e-05], + ['Mo100',1.29653664e-06], + ['Mo92',1.94919594e-06], + ['Mo94',1.2224222199999999e-06], + ['Mo95',2.11206138e-06], + ['Mo96',2.2185093799999997e-06], + ['Mo97',1.27498092e-06], + ['Mo98',3.2322935199999993e-06], + ['Mn55',0.0002202], + ['Cu63',1.77929865e-05], + ['Cu65',7.938013500000001e-06], + ['Si28',0.00014645150887199998], + ['Si29',7.436389764e-06], + ['Si30',4.9021013639999995e-06], + ['Ca40',2.0795783319999997e-06], + ['Ca42',1.3879444e-08], + ['Ca43',2.8960199999999997e-09], + ['Ca44',4.4748872e-08], + ['Ca46',8.5808e-11], + ['Ca48',4.0115239999999994e-09], + ['Cl35',2.2996101743999999e-07], + ['Cl37',7.355898256000001e-08], + ['Co59',8.241199999999999e-07]]) +# Material Name: Inner Axial reflector 1 +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',8.1353e-05], + ['U238',0.037936], + ['Cr50',7.153608e-05], + ['Cr52',0.001379502096], + ['Cr53',0.000156424464], + ['Cr54',3.893736e-05], + ['Ni58',0.00046930172553], + ['Ni60',0.00018077418447], + ['Ni61',7.85812863e-06], + ['Ni62',2.505515265e-05], + ['Ni64',6.38080872e-06], + ['Fe54',0.000354224535], + ['Fe56',0.005560567662000001], + ['Fe57',0.000128417757], + ['Fe58',1.7090046e-05], + ['C0',3.6728e-05], + ['Mo100',1.0348128e-06], + ['Mo92',1.5557238000000003e-06], + ['Mo94',9.756594e-07], + ['Mo95',1.6857126000000002e-06], + ['Mo96',1.7706726e-06], + ['Mo97',1.0176084e-06], + ['Mo98',2.5798104e-06], + ['Mn55',0.00014319], + ['Cu63',1.3651592999999999e-05], + ['Cu65',6.0904069999999985e-06], + ['Si28',9.797558906400001e-05], + ['Si29',4.974920868e-06], + ['Si30',3.279490068e-06]]) +# Material Name: Outer Axial Reflector 1 +# Depletable +m5 = mcdc.material(nuclides=[ + ['U235',8.1048e-05], + ['U238',0.037795], + ['Cr50',7.1940165e-05], + ['Cr52',0.001387294473], + ['Cr53',0.00015730805699999998], + ['Cr54',3.9157305e-05], + ['Ni58',0.00047184099389999996], + ['Ni60',0.00018175230609999998], + ['Ni61',7.900646899999999e-06], + ['Ni62',2.5190719500000003e-05], + ['Ni64',6.4153336e-06], + ['Fe54',0.000355978035], + ['Fe56',0.005588093862], + ['Fe57',0.000129053457], + ['Fe58',1.7174646e-05], + ['C0',3.6634e-05], + ['Mo100',1.04046432e-06], + ['Mo92',1.56422022e-06], + ['Mo94',9.8098786e-07], + ['Mo95',1.6949189400000002e-06], + ['Mo96',1.7803429399999998e-06], + ['Mo97',1.02316596e-06], + ['Mo98',2.59389976e-06], + ['Mn55',0.00014383], + ['Cu63',1.3708296000000001e-05], + ['Cu65',6.115704e-06], + ['Si28',9.7837244544e-05], + ['Si29',4.967896128e-06], + ['Si30',3.2748593280000005e-06]]) +# Material Name: Inner Axial reflector 2 +# Depletable +m6 = mcdc.material(nuclides=[ + ['U235',8.5866e-05], + ['U238',0.040055], + ['Cr50',6.2989465e-05], + ['Cr52',0.001214689133], + ['Cr53',0.000137735997], + ['Cr54',3.4285405e-05], + ['Ni58',0.00041358078287999996], + ['Ni60',0.00015931057711999997], + ['Ni61',6.925120479999999e-06], + ['Ni62',2.20803144e-05], + ['Ni64',5.62320512e-06], + ['Fe54',0.00030717228500000003], + ['Fe56',0.0048219479620000005], + ['Fe57',0.000111359807], + ['Fe58',1.4819946000000001e-05], + ['C0',2.7168000000000005e-05], + ['Mo100',9.784924799999999e-07], + ['Mo92',1.47105258e-06], + ['Mo94',9.225585399999999e-07], + ['Mo95',1.59396666e-06], + ['Mo96',1.6743026600000001e-06], + ['Mo97',9.6222444e-07], + ['Mo98',2.4394026399999997e-06], + ['Mn55',0.00012717], + ['Cu63',1.3185522000000003e-05], + ['Cu65',5.882478000000001e-06], + ['Si28',8.78054222504e-05], + ['Si29',4.4585088148e-06], + ['Si30',2.9390689348e-06]]) +# Material Name: Outer Axial Reflector 2 +# Depletable +m7 = mcdc.material(nuclides=[ + ['U235',8.474e-05], + ['U238',0.039527], + ['Cr50',6.385412e-05], + ['Cr52',0.001231363144], + ['Cr53',0.000139626696], + ['Cr54',3.475604e-05], + ['Ni58',0.00041910862715999994], + ['Ni60',0.00016143989284], + ['Ni61',7.01768036e-06], + ['Ni62',2.23754358e-05], + ['Ni64',5.69836384e-06], + ['Fe54',0.00031121702500000003], + ['Fe56',0.0048854417300000005], + ['Fe57',0.00011282615500000001], + ['Fe58',1.5015090000000002e-05], + ['C0',2.7315000000000002e-05], + ['Mo100',9.9554448e-07], + ['Mo92',1.4966883300000004e-06], + ['Mo94',9.3863579e-07], + ['Mo95',1.6217444100000004e-06], + ['Mo96',1.7034804100000002e-06], + ['Mo97',9.7899294e-07], + ['Mo98',2.4819136400000003e-06], + ['Mn55',0.00012863], + ['Cu63',1.3294087500000001e-05], + ['Cu65',5.9309124999999994e-06], + ['Si28',8.80636653544e-05], + ['Si29',4.4716216627999994e-06], + ['Si30',2.9477129828e-06]]) +# Material Name: Radial Reflector 1 +# Depletable +m8 = mcdc.material(nuclides=[ + ['U235',8.5846e-05], + ['U238',0.040046], + ['Cr50',5.119279e-05], + ['Cr52',0.000987201998], + ['Cr53',0.000111940782], + ['Cr54',2.786443e-05], + ['Ni58',0.00032389627482], + ['Ni60',0.00012476426518], + ['Ni61',5.42341622e-06], + ['Ni62',1.72922241e-05], + ['Ni64',4.40381968e-06], + ['Fe54',0.000247828], + ['Fe56',0.0038903695999999996], + ['Fe57',8.984559999999999e-05], + ['Fe58',1.19568e-05], + ['C0',1.8572e-05], + ['Mo100',7.971956159999999e-07], + ['Mo92',1.198493286e-06], + ['Mo94',7.516252179999999e-07], + ['Mo95',1.298633622e-06], + ['Mo96',1.3640848219999998e-06], + ['Mo97',7.83941748e-07], + ['Mo98',1.987425688e-06], + ['Mn55',0.00010493999999999998], + ['Cu63',1.18073625e-05], + ['Cu65',5.2676375e-06], + ['Si28',6.2425658908e-05], + ['Si29',3.169796846e-06], + ['Si30',2.089544246e-06]]) +# Material Name: Radial Reflector 2 +m9 = mcdc.material(nuclides=[ + ['Cr50',5.174895000000001e-05], + ['Cr52',0.00099792699], + ['Cr53',0.00011315691000000001], + ['Cr54',2.816715e-05], + ['Ni58',0.00032794004268], + ['Ni60',0.00012632191732], + ['Ni61',5.4911262799999994e-06], + ['Ni62',1.75081134e-05], + ['Ni64',4.45880032e-06], + ['Fe54',0.00025166232], + ['Fe56',0.003950560224], + ['Fe57',9.123566399999999e-05], + ['Fe58',1.2141792e-05], + ['C0',1.9752e-05], + ['Mo100',8.06013936e-07], + ['Mo92',1.211750631e-06], + ['Mo94',7.599394529999999e-07], + ['Mo95',1.312998687e-06], + ['Mo96',1.3791738869999999e-06], + ['Mo97',7.926134579999998e-07], + ['Mo98',2.009409948e-06], + ['Mn55',0.00010598999999999999], + ['Cu63',1.1884119e-05], + ['Cu65',5.3018810000000005e-06], + ['Si28',6.34438745752e-05], + ['Si29',3.2214989324e-06], + ['Si30',2.1236264923999997e-06]]) +# Material Name: Empty Matrix +m10 = mcdc.material(nuclides=[ + ['Cr50',5.174895000000001e-05], + ['Cr52',0.00099792699], + ['Cr53',0.00011315691000000001], + ['Cr54',2.816715e-05], + ['Ni58',0.00032794004268], + ['Ni60',0.00012632191732], + ['Ni61',5.4911262799999994e-06], + ['Ni62',1.75081134e-05], + ['Ni64',4.45880032e-06], + ['Fe54',0.00025166232], + ['Fe56',0.003950560224], + ['Fe57',9.123566399999999e-05], + ['Fe58',1.2141792e-05], + ['C0',1.9752e-05], + ['Mo100',8.06013936e-07], + ['Mo92',1.211750631e-06], + ['Mo94',7.599394529999999e-07], + ['Mo95',1.312998687e-06], + ['Mo96',1.3791738869999999e-06], + ['Mo97',7.926134579999998e-07], + ['Mo98',2.009409948e-06], + ['Mn55',0.00010598999999999999], + ['Cu63',1.1884119e-05], + ['Cu65',5.3018810000000005e-06], + ['Si28',6.34438745752e-05], + ['Si29',3.2214989324e-06], + ['Si30',2.1236264923999997e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=24.3435, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=75.0028, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=78.0496, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=111.5583, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=140.2589, bc='vacuum') +s6 = mcdc.surface('plane-z', z=0.0, bc='reflective') +s7 = mcdc.surface('plane-z', z=76.2813, bc='interface') +s8 = mcdc.surface('plane-z', z=101.7257, bc='interface') +s9 = mcdc.surface('plane-z', z=106.68, bc='interface') +s10 = mcdc.surface('plane-z', z=110.5357, bc='interface') +s11 = mcdc.surface('plane-z', z=121.92, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & +s6 & -s7, fill=m1) +c2 = mcdc.cell(+s1 & -s2 & +s6 & -s7, fill=m2) +c3 = mcdc.cell(+s2 & -s3 & +s6 & -s7, fill=m3) +c4 = mcdc.cell(-s1 & +s7 & -s8, fill=m4) +c5 = mcdc.cell(+s1 & -s3 & +s7 & -s8, fill=m5) +c6 = mcdc.cell(-s1 & +s8 & -s10, fill=m6) +c7 = mcdc.cell(+s1 & -s3 & +s8 & -s10, fill=m7) +c8 = mcdc.cell(+s3 & -s4 & +s6 & -s9, fill=m8) +c9 = mcdc.cell(+s3 & -s4 & +s9 & -s10, fill=m9) +c10 = mcdc.cell(-s4 & +s10 & -s11, fill=m10) +c11 = mcdc.cell(+s4 & -s5 & +s6 & -s11, fill=m10) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-141.0,141.0], y=[-141.0,141.0], z=[0.0,122.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-comp-fast-002/openmc/generate_materials.py b/icsbep/openmc/mix-comp-fast-002/openmc/generate_materials.py new file mode 100644 index 0000000..27b9557 --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-002/openmc/generate_materials.py @@ -0,0 +1,187 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Inner Core 1" +mat.set_density('sum') +mat.add_nuclide('Pu240', 3.2178E-04) +mat.add_nuclide('Pu241', 5.3569E-05) +mat.add_nuclide('U235', 1.1872E-05) +mat.add_nuclide('U238', 5.5620E-03) +mat.add_nuclide('Pu239', 8.3844E-04) +mat.add_nuclide('Pu238', 1.1083E-06) +mat.add_nuclide('Pu242', 1.7447E-05) +mat.add_nuclide('Am241', 1.4681E-05) +mat.add_element('Cr', 2.6792E-03) +mat.add_element('Ni', 1.1908E-03) +mat.add_element('Fe', 1.2805E-02) +mat.add_element('Al', 4.1057E-06) +mat.add_element('Na', 9.1676E-03) +mat.add_element('O', 1.3684E-02) +mat.add_element('C', 3.6621E-05) +mat.add_element('Mo', 2.3662E-04) +mat.add_element('Mn', 2.2447E-04) +mat.add_element('Cu', 2.4580E-05) +mat.add_element('Si', 1.6182E-04) +mat.add_element('Ca', 2.1044E-06) +mat.add_element('Cl', 2.9484E-07) +mat.add_element('Co', 8.2889E-07) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Outer Core 1" +mat.set_density('sum') +mat.add_nuclide('Pu240', 1.1749E-04) +mat.add_nuclide('Pu241', 1.4641E-05) +mat.add_nuclide('U235', 1.2575E-05) +mat.add_nuclide('U238', 5.7820E-03) +mat.add_nuclide('Pu239', 8.8583E-04) +mat.add_nuclide('Pu238', 4.6444E-07) +mat.add_nuclide('Pu242', 1.7620E-06) +mat.add_nuclide('Am241', 2.9643E-06) +mat.add_element('Cr', 2.6909E-03) +mat.add_element('Ni', 1.1885E-03) +mat.add_element('Fe', 1.3230E-02) +mat.add_element('Al', 1.8593E-05) +mat.add_element('Na', 9.0718E-03) +mat.add_element('O', 1.4192E-02) +mat.add_element('C', 3.3605E-05) +mat.add_element('Mo', 2.3875E-04) +mat.add_element('Mn', 2.2395E-04) +mat.add_element('Cu', 2.4882E-05) +mat.add_element('Si', 1.5377E-04) +mat.add_element('Ca', 2.0828E-06) +mat.add_element('Cl', 2.9546E-07) +mat.add_element('Co', 5.4095E-08) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Pu-Al ring" +mat.set_density('sum') +mat.add_nuclide('Pu240', 5.0694E-05) +mat.add_nuclide('Pu241', 2.8433E-06) +mat.add_nuclide('U235', 1.2151E-05) +mat.add_nuclide('U238', 5.7042E-03) +mat.add_nuclide('Pu239', 1.0697E-03) +mat.add_nuclide('Pu238', 1.6248E-09) +mat.add_nuclide('Pu242', 1.1005E-07) +mat.add_nuclide('Am241', 1.9758E-06) +mat.add_element('Cr', 2.6230E-03) +mat.add_element('Ni', 1.1648E-03) +mat.add_element('Fe', 1.3160E-02) +mat.add_element('Al', 1.1477E-04) +mat.add_element('Na', 9.3420E-03) +mat.add_element('O', 1.4386E-02) +mat.add_element('C', 4.0021E-05) +mat.add_element('Mo', 1.3306E-05) +mat.add_element('Mn', 2.2020E-04) +mat.add_element('Cu', 2.5731E-05) +mat.add_element('Si', 1.5879E-04) +mat.add_element('Ca', 2.1452E-06) +mat.add_element('Cl', 3.0352E-07) +mat.add_element('Co', 8.2412E-07) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Inner Axial reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.1353E-05) +mat.add_nuclide('U238', 3.7936E-02) +mat.add_element('Cr', 1.6464E-03) +mat.add_element('Ni', 6.8937E-04) +mat.add_element('Fe', 6.0603E-03) +mat.add_element('C', 3.6728E-05) +mat.add_element('Mo', 1.0620E-05) +mat.add_element('Mn', 1.4319E-04) +mat.add_element('Cu', 1.9742E-05) +mat.add_element('Si', 1.0623E-04) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Inner Axial reflector 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.5866E-05) +mat.add_nuclide('U238', 4.0055E-02) +mat.add_element('Cr', 1.4497E-03) +mat.add_element('Ni', 6.0752E-04) +mat.add_element('Fe', 5.2553E-03) +mat.add_element('C', 2.7168E-05) +mat.add_element('Mo', 1.0042E-05) +mat.add_element('Mn', 1.2717E-04) +mat.add_element('Cu', 1.9068E-05) +mat.add_element('Si', 9.5203E-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Outer Axial Reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.1048E-05) +mat.add_nuclide('U238', 3.7795E-02) +mat.add_element('Cr', 1.6557E-03) +mat.add_element('Ni', 6.9310E-04) +mat.add_element('Fe', 6.0903E-03) +mat.add_element('C', 3.6634E-05) +mat.add_element('Mo', 1.0678E-05) +mat.add_element('Mn', 1.4383E-04) +mat.add_element('Cu', 1.9824E-05) +mat.add_element('Si', 1.0608E-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Outer Axial Reflector 2" +mat.set_density('sum') +mat.add_nuclide('U235', 8.4740E-05) +mat.add_nuclide('U238', 3.9527E-02) +mat.add_element('Cr', 1.4696E-03) +mat.add_element('Ni', 6.1564E-04) +mat.add_element('Fe', 5.3245E-03) +mat.add_element('C', 2.7315E-05) +mat.add_element('Mo', 1.0217E-05) +mat.add_element('Mn', 1.2863E-04) +mat.add_element('Cu', 1.9225E-05) +mat.add_element('Si', 9.5483E-05) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Radial Reflector 1" +mat.set_density('sum') +mat.add_nuclide('U235', 8.5846E-05) +mat.add_nuclide('U238', 4.0046E-02) +mat.add_element('Cr', 1.1782E-03) +mat.add_element('Ni', 4.7578E-04) +mat.add_element('Fe', 4.2400E-03) +mat.add_element('C', 1.8572E-05) +mat.add_element('Mo', 8.1814E-06) +mat.add_element('Mn', 1.0494E-04) +mat.add_element('Cu', 1.7075E-05) +mat.add_element('Si', 6.7685E-05) +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "Radial Reflector 2" +mat.set_density('sum') +mat.add_element('Cr', 1.1910E-03) +mat.add_element('Ni', 4.8172E-04) +mat.add_element('Fe', 4.3056E-03) +mat.add_element('C', 1.9752E-05) +mat.add_element('Mo', 8.2719E-06) +mat.add_element('Mn', 1.0599E-04) +mat.add_element('Cu', 1.7186E-05) +mat.add_element('Si', 6.8789E-05) +mats.append(mat) + +mat = openmc.Material(10) +mat.name = "Empty Matrix" +mat.set_density('sum') +mat.add_element('Cr', 1.1910E-03) +mat.add_element('Ni', 4.8172E-04) +mat.add_element('Fe', 4.3056E-03) +mat.add_element('C', 1.9752E-05) +mat.add_element('Mo', 8.2719E-06) +mat.add_element('Mn', 1.0599E-04) +mat.add_element('Cu', 1.7186E-05) +mat.add_element('Si', 6.8789E-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-fast-002/openmc/geometry.xml b/icsbep/openmc/mix-comp-fast-002/openmc/geometry.xml new file mode 100644 index 0000000..76b8566 --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-002/openmc/geometry.xml @@ -0,0 +1,56 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-fast-002/openmc/materials.xml b/icsbep/openmc/mix-comp-fast-002/openmc/materials.xml new file mode 100644 index 0000000..ad1048c --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-002/openmc/materials.xml @@ -0,0 +1,376 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-fast-002/openmc/settings.xml b/icsbep/openmc/mix-comp-fast-002/openmc/settings.xml new file mode 100644 index 0000000..591e8be --- /dev/null +++ b/icsbep/openmc/mix-comp-fast-002/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -141. -141. 0. 141. 141. 122. + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-30.py b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-30.py new file mode 100644 index 0000000..c1da847 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-30.py @@ -0,0 +1,170 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2-PuO2 Mixture +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8836e-08], + ['Pu239',0.00039462], + ['Pu240',3.3206e-05], + ['Pu242',1.1882e-07], + ['Am241',1.4954e-06], + ['U235',0.00014886], + ['U238',0.020611], + ['O16',0.043779]]) +# Material Name: Natural UO2 Layer +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00014824], + ['U238',0.020525], + ['O16',0.041943]]) +# Material Name: Cladding +m3 = mcdc.material(nuclides=[ + ['Sn112',4.687816e-06], + ['Sn114',3.189648e-06], + ['Sn115',1.643152e-06], + ['Sn116',7.0268912e-05], + ['Sn117',3.7115904e-05], + ['Sn118',0.00011705041599999999], + ['Sn119',4.1513752000000004e-05], + ['Sn120',0.00015745262399999998], + ['Sn122',2.2375864e-05], + ['Sn124',2.7981912e-05], + ['Fe54',5.5902749000000005e-06], + ['Fe56',8.775536068e-05], + ['Fe57',2.02665398e-06], + ['Fe58',2.6971044e-07], + ['Cr50',3.3062408500000004e-06], + ['Cr52',6.375756377000001e-05], + ['Cr53',7.2295959300000005e-06], + ['Cr54',1.7995994500000002e-06], + ['Ni58',2.0651808383999998e-05], + ['Ni60',7.955039615999999e-06], + ['Ni61',3.4580006399999995e-07], + ['Ni62',1.10256192e-06], + ['Ni64',2.80790016e-07], + ['Zr90',0.021928504499999998], + ['Zr91',0.0047820762], + ['Zr92',0.0073095015], + ['Zr94',0.007407529800000001], + ['Zr96',0.001193388]]) +# Material Name: Moderator +# S(a,b): c_H_in_H2O (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.066706], + ['O16',0.033340359213], + ['O17',1.2640787000000002e-05], + ['B10',1.8706e-08], + ['B11',7.577e-08]]) +# Material Name: 6061 Aluminum +m5 = mcdc.material(nuclides=[ + ['Si28',0.00031917925357600004], + ['Si29',1.6207011812000003e-05], + ['Si30',1.0683734612e-05], + ['Fe54',5.933844e-06], + ['Fe56',9.31486608e-05], + ['Fe57',2.1512088e-06], + ['Fe58',2.862864e-07], + ['Cu63',4.40699865e-05], + ['Cu65',1.96610135e-05], + ['Mn55',2.2115e-05], + ['Mg24',0.0005262163101000001], + ['Mg25',6.6784302e-05], + ['Mg26',7.350938790000001e-05], + ['Cr50',2.7073695000000004e-06], + ['Cr52',5.220892590000001e-05], + ['Cr53',5.9200731000000005e-06], + ['Cr54',1.4736315e-06], + ['Zn64',1.5226473899999998e-05], + ['Zn66',8.587149099999998e-06], + ['Zn67',1.2510667999999998e-06], + ['Zn68',5.713411499999999e-06], + ['Zn70',1.888987e-07], + ['Ti46',2.0934375000000002e-06], + ['Ti47',1.8879000000000002e-06], + ['Ti48',1.8706449999999998e-05], + ['Ti49',1.3727875e-06], + ['Ti50',1.314425e-06], + ['Al27',0.058433]]) +# Material Name: Lead +m6 = mcdc.material(nuclides=[ + ['Pb204',0.000450436], + ['Pb206',0.007753934], + ['Pb207',0.007110454], + ['Pb208',0.016859176]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-30.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s4 = mcdc.surface('plane-z', z=2.8575, bc='interface') +s5 = mcdc.surface('plane-z', z=3.175, bc='interface') +s6 = mcdc.surface('plane-z', z=3.556, bc='interface') +s7 = mcdc.surface('plane-z', z=4.056, bc='interface') +s8 = mcdc.surface('plane-z', z=5.715, bc='interface') +s9 = mcdc.surface('plane-z', z=92.3925, bc='interface') +s10 = mcdc.surface('plane-z', z=94.9325, bc='interface') +s11 = mcdc.surface('plane-z', z=94.996, bc='interface') +s12 = mcdc.surface('plane-z', z=95.8215, bc='interface') +s14 = mcdc.surface('plane-z', z=96.774, bc='interface') +s15 = mcdc.surface('plane-z', z=110.236, bc='vacuum') +s21 = mcdc.surface('plane-x', x=0.0, bc='reflective') +s23 = mcdc.surface('plane-y', y=0.0, bc='reflective') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.0, bc='vacuum') +s35 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.64135, bc='interface') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.71755, bc='interface') +s37 = mcdc.surface('plane-x', x=-0.73025, bc='interface') +s38 = mcdc.surface('plane-x', x=0.73025, bc='interface') +s39 = mcdc.surface('plane-y', y=-0.73025, bc='interface') +s40 = mcdc.surface('plane-y', y=0.73025, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s21 & +s23 & -s25 & +s1 & -s2, fill=m4) +c2 = mcdc.cell(+s21 & +s23 & -s25 & +s2 & -s4, fill=m5) +c4 = mcdc.cell(+s21 & +s23 & -s25 & +s12 & -s14, fill=m6) +c5 = mcdc.cell(+s21 & +s23 & -s25 & +s14 & -s15, fill=m4) +c21 = mcdc.cell(-s6 & -s36, fill=m3) +c22 = mcdc.cell(+s6 & -s7 & -s35, fill=m2) +c23 = mcdc.cell(+s7 & -s11 & -s35, fill=m1) +c24 = mcdc.cell(+s6 & -s11 & +s35 & -s36, fill=m3) +c25 = mcdc.cell(+s11 & -s36, fill=m3) +c26 = mcdc.cell(-s5 & +s36, fill=m4) +c27 = mcdc.cell(+s5 & -s8 & -s37, fill=m5) +c28 = mcdc.cell(+s5 & -s8 & +s38, fill=m5) +c29 = mcdc.cell(+s5 & -s8 & -s39 & +s37 & -s38, fill=m5) +c30 = mcdc.cell(+s5 & -s8 & +s40 & +s37 & -s38, fill=m5) +c31 = mcdc.cell(+s5 & -s8 & +s37 & -s38 & +s39 & -s40 & +s36, fill=m4) +c32 = mcdc.cell(+s8 & -s9 & +s36, fill=m4) +c33 = mcdc.cell(+s9 & -s10 & -s37, fill=m5) +c34 = mcdc.cell(+s9 & -s10 & +s38, fill=m5) +c35 = mcdc.cell(+s9 & -s10 & -s39 & +s37 & -s38, fill=m5) +c36 = mcdc.cell(+s9 & -s10 & +s40 & +s37 & -s38, fill=m5) +c37 = mcdc.cell(+s9 & -s10 & +s37 & -s38 & +s39 & -s40 & +s36, fill=m4) +c38 = mcdc.cell(+s10 & +s36, fill=m4) +c41 = mcdc.cell(-s5, fill=m4) +c42 = mcdc.cell(+s5 & -s8 & -s37, fill=m5) +c43 = mcdc.cell(+s5 & -s8 & +s38, fill=m5) +c44 = mcdc.cell(+s5 & -s8 & -s39 & +s37 & -s38, fill=m5) +c45 = mcdc.cell(+s5 & -s8 & +s40 & +s37 & -s38, fill=m5) +c46 = mcdc.cell(+s5 & -s8 & +s37 & -s38 & +s39 & -s40, fill=m4) +c47 = mcdc.cell(+s8 & -s9, fill=m4) +c48 = mcdc.cell(+s9 & -s10 & -s37, fill=m5) +c49 = mcdc.cell(+s9 & -s10 & +s38, fill=m5) +c50 = mcdc.cell(+s9 & -s10 & -s39 & +s37 & -s38, fill=m5) +c51 = mcdc.cell(+s9 & -s10 & +s40 & +s37 & -s38, fill=m5) +c52 = mcdc.cell(+s9 & -s10 & +s37 & -s38 & +s39 & -s40, fill=m4) +c53 = mcdc.cell(+s10, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 11 +Lattice11 = mcdc.lattice(x=[-0.889, 1.778, 29], y=[-0.889, 1.778, 29], \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-31.py b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-31.py new file mode 100644 index 0000000..2aa2c48 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-31.py @@ -0,0 +1,170 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2-PuO2 Mixture +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8836e-08], + ['Pu239',0.00039462], + ['Pu240',3.3206e-05], + ['Pu242',1.1882e-07], + ['Am241',1.4954e-06], + ['U235',0.00014886], + ['U238',0.020611], + ['O16',0.043779]]) +# Material Name: Natural UO2 Layer +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00014824], + ['U238',0.020525], + ['O16',0.041943]]) +# Material Name: Cladding +m3 = mcdc.material(nuclides=[ + ['Sn112',4.687816e-06], + ['Sn114',3.189648e-06], + ['Sn115',1.643152e-06], + ['Sn116',7.0268912e-05], + ['Sn117',3.7115904e-05], + ['Sn118',0.00011705041599999999], + ['Sn119',4.1513752000000004e-05], + ['Sn120',0.00015745262399999998], + ['Sn122',2.2375864e-05], + ['Sn124',2.7981912e-05], + ['Fe54',5.5902749000000005e-06], + ['Fe56',8.775536068e-05], + ['Fe57',2.02665398e-06], + ['Fe58',2.6971044e-07], + ['Cr50',3.3062408500000004e-06], + ['Cr52',6.375756377000001e-05], + ['Cr53',7.2295959300000005e-06], + ['Cr54',1.7995994500000002e-06], + ['Ni58',2.0651808383999998e-05], + ['Ni60',7.955039615999999e-06], + ['Ni61',3.4580006399999995e-07], + ['Ni62',1.10256192e-06], + ['Ni64',2.80790016e-07], + ['Zr90',0.021928504499999998], + ['Zr91',0.0047820762], + ['Zr92',0.0073095015], + ['Zr94',0.007407529800000001], + ['Zr96',0.001193388]]) +# Material Name: Moderator +# S(a,b): c_H_in_H2O (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.066685], + ['O16',0.0333873414], + ['O17',1.2658599999999998e-05], + ['B10',7.5838e-06], + ['B11',3.0718e-05]]) +# Material Name: 6061 Aluminum +m5 = mcdc.material(nuclides=[ + ['Si28',0.00031917925357600004], + ['Si29',1.6207011812000003e-05], + ['Si30',1.0683734612e-05], + ['Fe54',5.933844e-06], + ['Fe56',9.31486608e-05], + ['Fe57',2.1512088e-06], + ['Fe58',2.862864e-07], + ['Cu63',4.40699865e-05], + ['Cu65',1.96610135e-05], + ['Mn55',2.2115e-05], + ['Mg24',0.0005262163101000001], + ['Mg25',6.6784302e-05], + ['Mg26',7.350938790000001e-05], + ['Cr50',2.7073695000000004e-06], + ['Cr52',5.220892590000001e-05], + ['Cr53',5.9200731000000005e-06], + ['Cr54',1.4736315e-06], + ['Zn64',1.5226473899999998e-05], + ['Zn66',8.587149099999998e-06], + ['Zn67',1.2510667999999998e-06], + ['Zn68',5.713411499999999e-06], + ['Zn70',1.888987e-07], + ['Ti46',2.0934375000000002e-06], + ['Ti47',1.8879000000000002e-06], + ['Ti48',1.8706449999999998e-05], + ['Ti49',1.3727875e-06], + ['Ti50',1.314425e-06], + ['Al27',0.058433]]) +# Material Name: Lead +m6 = mcdc.material(nuclides=[ + ['Pb204',0.000450436], + ['Pb206',0.007753934], + ['Pb207',0.007110454], + ['Pb208',0.016859176]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-30.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s4 = mcdc.surface('plane-z', z=2.8575, bc='interface') +s5 = mcdc.surface('plane-z', z=3.175, bc='interface') +s6 = mcdc.surface('plane-z', z=3.556, bc='interface') +s7 = mcdc.surface('plane-z', z=4.056, bc='interface') +s8 = mcdc.surface('plane-z', z=5.715, bc='interface') +s9 = mcdc.surface('plane-z', z=92.3925, bc='interface') +s10 = mcdc.surface('plane-z', z=94.9325, bc='interface') +s11 = mcdc.surface('plane-z', z=94.996, bc='interface') +s12 = mcdc.surface('plane-z', z=95.8215, bc='interface') +s14 = mcdc.surface('plane-z', z=96.774, bc='interface') +s15 = mcdc.surface('plane-z', z=110.236, bc='vacuum') +s21 = mcdc.surface('plane-x', x=0.0, bc='reflective') +s23 = mcdc.surface('plane-y', y=0.0, bc='reflective') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=60.0, bc='vacuum') +s35 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.64135, bc='interface') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.71755, bc='interface') +s37 = mcdc.surface('plane-x', x=-0.73025, bc='interface') +s38 = mcdc.surface('plane-x', x=0.73025, bc='interface') +s39 = mcdc.surface('plane-y', y=-0.73025, bc='interface') +s40 = mcdc.surface('plane-y', y=0.73025, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s21 & +s23 & -s25 & +s1 & -s2, fill=m4) +c2 = mcdc.cell(+s21 & +s23 & -s25 & +s2 & -s4, fill=m5) +c4 = mcdc.cell(+s21 & +s23 & -s25 & +s12 & -s14, fill=m6) +c5 = mcdc.cell(+s21 & +s23 & -s25 & +s14 & -s15, fill=m4) +c21 = mcdc.cell(-s6 & -s36, fill=m3) +c22 = mcdc.cell(+s6 & -s7 & -s35, fill=m2) +c23 = mcdc.cell(+s7 & -s11 & -s35, fill=m1) +c24 = mcdc.cell(+s6 & -s11 & +s35 & -s36, fill=m3) +c25 = mcdc.cell(+s11 & -s36, fill=m3) +c26 = mcdc.cell(-s5 & +s36, fill=m4) +c27 = mcdc.cell(+s5 & -s8 & -s37, fill=m5) +c28 = mcdc.cell(+s5 & -s8 & +s38, fill=m5) +c29 = mcdc.cell(+s5 & -s8 & -s39 & +s37 & -s38, fill=m5) +c30 = mcdc.cell(+s5 & -s8 & +s40 & +s37 & -s38, fill=m5) +c31 = mcdc.cell(+s5 & -s8 & +s37 & -s38 & +s39 & -s40 & +s36, fill=m4) +c32 = mcdc.cell(+s8 & -s9 & +s36, fill=m4) +c33 = mcdc.cell(+s9 & -s10 & -s37, fill=m5) +c34 = mcdc.cell(+s9 & -s10 & +s38, fill=m5) +c35 = mcdc.cell(+s9 & -s10 & -s39 & +s37 & -s38, fill=m5) +c36 = mcdc.cell(+s9 & -s10 & +s40 & +s37 & -s38, fill=m5) +c37 = mcdc.cell(+s9 & -s10 & +s37 & -s38 & +s39 & -s40 & +s36, fill=m4) +c38 = mcdc.cell(+s10 & +s36, fill=m4) +c41 = mcdc.cell(-s5, fill=m4) +c42 = mcdc.cell(+s5 & -s8 & -s37, fill=m5) +c43 = mcdc.cell(+s5 & -s8 & +s38, fill=m5) +c44 = mcdc.cell(+s5 & -s8 & -s39 & +s37 & -s38, fill=m5) +c45 = mcdc.cell(+s5 & -s8 & +s40 & +s37 & -s38, fill=m5) +c46 = mcdc.cell(+s5 & -s8 & +s37 & -s38 & +s39 & -s40, fill=m4) +c47 = mcdc.cell(+s8 & -s9, fill=m4) +c48 = mcdc.cell(+s9 & -s10 & -s37, fill=m5) +c49 = mcdc.cell(+s9 & -s10 & +s38, fill=m5) +c50 = mcdc.cell(+s9 & -s10 & -s39 & +s37 & -s38, fill=m5) +c51 = mcdc.cell(+s9 & -s10 & +s40 & +s37 & -s38, fill=m5) +c52 = mcdc.cell(+s9 & -s10 & +s37 & -s38 & +s39 & -s40, fill=m4) +c53 = mcdc.cell(+s10, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 11 +Lattice11 = mcdc.lattice(x=[-0.889, 1.778, 35], y=[-0.889, 1.778, 35], \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-32.py b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-32.py new file mode 100644 index 0000000..fc744a7 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-32.py @@ -0,0 +1,190 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2-PuO2 Mixture +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8836e-08], + ['Pu239',0.00039462], + ['Pu240',3.3206e-05], + ['Pu242',1.1882e-07], + ['Am241',1.4954e-06], + ['U235',0.00014886], + ['U238',0.020611], + ['O16',0.043779]]) +# Material Name: Natural UO2 Layer +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00014824], + ['U238',0.020525], + ['O16',0.041943]]) +# Material Name: Cladding +m3 = mcdc.material(nuclides=[ + ['Sn112',4.687816e-06], + ['Sn114',3.189648e-06], + ['Sn115',1.643152e-06], + ['Sn116',7.0268912e-05], + ['Sn117',3.7115904e-05], + ['Sn118',0.00011705041599999999], + ['Sn119',4.1513752000000004e-05], + ['Sn120',0.00015745262399999998], + ['Sn122',2.2375864e-05], + ['Sn124',2.7981912e-05], + ['Fe54',5.5902749000000005e-06], + ['Fe56',8.775536068e-05], + ['Fe57',2.02665398e-06], + ['Fe58',2.6971044e-07], + ['Cr50',3.3062408500000004e-06], + ['Cr52',6.375756377000001e-05], + ['Cr53',7.2295959300000005e-06], + ['Cr54',1.7995994500000002e-06], + ['Ni58',2.0651808383999998e-05], + ['Ni60',7.955039615999999e-06], + ['Ni61',3.4580006399999995e-07], + ['Ni62',1.10256192e-06], + ['Ni64',2.80790016e-07], + ['Zr90',0.021928504499999998], + ['Zr91',0.0047820762], + ['Zr92',0.0073095015], + ['Zr94',0.007407529800000001], + ['Zr96',0.001193388]]) +# Material Name: Moderator +# S(a,b): c_H_in_H2O (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.066706], + ['O16',0.033340359213], + ['O17',1.2640787e-05], + ['B10',9.9034e-09], + ['B11',4.0114e-08]]) +# Material Name: 6061 Aluminum +m5 = mcdc.material(nuclides=[ + ['Si28',0.00031917925357600004], + ['Si29',1.6207011812000003e-05], + ['Si30',1.0683734612e-05], + ['Fe54',5.933844e-06], + ['Fe56',9.31486608e-05], + ['Fe57',2.1512088e-06], + ['Fe58',2.862864e-07], + ['Cu63',4.40699865e-05], + ['Cu65',1.96610135e-05], + ['Mn55',2.2115e-05], + ['Mg24',0.0005262163101000001], + ['Mg25',6.6784302e-05], + ['Mg26',7.350938790000001e-05], + ['Cr50',2.7073695000000004e-06], + ['Cr52',5.220892590000001e-05], + ['Cr53',5.9200731000000005e-06], + ['Cr54',1.4736315e-06], + ['Zn64',1.5226473899999998e-05], + ['Zn66',8.587149099999998e-06], + ['Zn67',1.2510667999999998e-06], + ['Zn68',5.713411499999999e-06], + ['Zn70',1.888987e-07], + ['Ti46',2.0934375000000002e-06], + ['Ti47',1.8879000000000002e-06], + ['Ti48',1.8706449999999998e-05], + ['Ti49',1.3727875e-06], + ['Ti50',1.314425e-06], + ['Al27',0.058433]]) +# Material Name: Lead +m6 = mcdc.material(nuclides=[ + ['Pb204',0.000450436], + ['Pb206',0.007753934], + ['Pb207',0.007110454], + ['Pb208',0.016859176]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-30.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s4 = mcdc.surface('plane-z', z=2.8575, bc='interface') +s5 = mcdc.surface('plane-z', z=3.175, bc='interface') +s6 = mcdc.surface('plane-z', z=3.556, bc='interface') +s7 = mcdc.surface('plane-z', z=4.056, bc='interface') +s8 = mcdc.surface('plane-z', z=5.715, bc='interface') +s9 = mcdc.surface('plane-z', z=92.3925, bc='interface') +s10 = mcdc.surface('plane-z', z=94.9325, bc='interface') +s11 = mcdc.surface('plane-z', z=94.996, bc='interface') +s12 = mcdc.surface('plane-z', z=95.8215, bc='interface') +s14 = mcdc.surface('plane-z', z=96.774, bc='interface') +s15 = mcdc.surface('plane-z', z=100.711, bc='vacuum') +s21 = mcdc.surface('plane-x', x=0.0, bc='reflective') +s23 = mcdc.surface('plane-y', y=0.0, bc='reflective') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=60.0, bc='vacuum') +s35 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.64135, bc='interface') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.71755, bc='interface') +s37 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.16204514, bc='interface') +s38 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.04709786, bc='interface') +s39 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.16204514, bc='interface') +s40 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.04709786, bc='interface') +s41 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.16204514, bc='interface') +s42 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.04709786, bc='interface') +s43 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.16204514, bc='interface') +s44 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.04709786, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s21 & +s23 & -s25 & +s1 & -s2, fill=m4) +c2 = mcdc.cell(+s21 & +s23 & -s25 & +s2 & -s4, fill=m5) +c4 = mcdc.cell(+s21 & +s23 & -s25 & +s12 & -s14, fill=m6) +c5 = mcdc.cell(+s21 & +s23 & -s25 & +s14 & -s15, fill=m4) +c21 = mcdc.cell(-s6 & -s36, fill=m3) +c22 = mcdc.cell(+s6 & -s7 & -s35, fill=m2) +c23 = mcdc.cell(+s7 & -s11 & -s35, fill=m1) +c24 = mcdc.cell(+s6 & -s11 & +s35 & -s36, fill=m3) +c25 = mcdc.cell(+s11 & -s36, fill=m3) +c26 = mcdc.cell(-s5 & +s36, fill=m4) +c27 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c28 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c29 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c30 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c31 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c32 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c33 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c34 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c35 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c36 = mcdc.cell(+s8 & -s9 & +s36, fill=m4) +c37 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c38 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c39 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c40 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c41 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c42 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c43 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c44 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c45 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c46 = mcdc.cell(+s10 & +s36, fill=m4) +c51 = mcdc.cell(-s5, fill=m4) +c52 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c53 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c54 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c55 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c56 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44, fill=m4) +c57 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c58 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c59 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c60 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c61 = mcdc.cell(+s8 & -s9, fill=m4) +c62 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c63 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c64 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c65 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c66 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44, fill=m4) +c67 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c68 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c69 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c70 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c71 = mcdc.cell(+s10, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 11 +Lattice11 = mcdc.lattice(x=[-1.10457, 2.20914, 28], y=[-1.10457, 2.20914, 28], \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-33.py b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-33.py new file mode 100644 index 0000000..8e0c196 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-33.py @@ -0,0 +1,190 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2-PuO2 Mixture +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8836e-08], + ['Pu239',0.00039462], + ['Pu240',3.3206e-05], + ['Pu242',1.1882e-07], + ['Am241',1.4954e-06], + ['U235',0.00014886], + ['U238',0.020611], + ['O16',0.043779]]) +# Material Name: Natural UO2 Layer +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00014824], + ['U238',0.020525], + ['O16',0.041943]]) +# Material Name: Cladding +m3 = mcdc.material(nuclides=[ + ['Sn112',4.687816e-06], + ['Sn114',3.189648e-06], + ['Sn115',1.643152e-06], + ['Sn116',7.0268912e-05], + ['Sn117',3.7115904e-05], + ['Sn118',0.00011705041599999999], + ['Sn119',4.1513752000000004e-05], + ['Sn120',0.00015745262399999998], + ['Sn122',2.2375864e-05], + ['Sn124',2.7981912e-05], + ['Fe54',5.5902749000000005e-06], + ['Fe56',8.775536068e-05], + ['Fe57',2.02665398e-06], + ['Fe58',2.6971044e-07], + ['Cr50',3.3062408500000004e-06], + ['Cr52',6.375756377000001e-05], + ['Cr53',7.2295959300000005e-06], + ['Cr54',1.7995994500000002e-06], + ['Ni58',2.0651808383999998e-05], + ['Ni60',7.955039615999999e-06], + ['Ni61',3.4580006399999995e-07], + ['Ni62',1.10256192e-06], + ['Ni64',2.80790016e-07], + ['Zr90',0.021928504499999998], + ['Zr91',0.0047820762], + ['Zr92',0.0073095015], + ['Zr94',0.007407529800000001], + ['Zr96',0.001193388]]) +# Material Name: Moderator +# S(a,b): c_H_in_H2O (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.066672], + ['O16',0.033414331166999996], + ['O17',1.2668833e-05], + ['B10',1.2034e-05], + ['B11',4.8746e-05]]) +# Material Name: 6061 Aluminum +m5 = mcdc.material(nuclides=[ + ['Si28',0.00031917925357600004], + ['Si29',1.6207011812000003e-05], + ['Si30',1.0683734612e-05], + ['Fe54',5.933844e-06], + ['Fe56',9.31486608e-05], + ['Fe57',2.1512088e-06], + ['Fe58',2.862864e-07], + ['Cu63',4.40699865e-05], + ['Cu65',1.96610135e-05], + ['Mn55',2.2115e-05], + ['Mg24',0.0005262163101000001], + ['Mg25',6.6784302e-05], + ['Mg26',7.350938790000001e-05], + ['Cr50',2.7073695000000004e-06], + ['Cr52',5.220892590000001e-05], + ['Cr53',5.9200731000000005e-06], + ['Cr54',1.4736315e-06], + ['Zn64',1.5226473899999998e-05], + ['Zn66',8.587149099999998e-06], + ['Zn67',1.2510667999999998e-06], + ['Zn68',5.713411499999999e-06], + ['Zn70',1.888987e-07], + ['Ti46',2.0934375000000002e-06], + ['Ti47',1.8879000000000002e-06], + ['Ti48',1.8706449999999998e-05], + ['Ti49',1.3727875e-06], + ['Ti50',1.314425e-06], + ['Al27',0.058433]]) +# Material Name: Lead +m6 = mcdc.material(nuclides=[ + ['Pb204',0.000450436], + ['Pb206',0.007753934], + ['Pb207',0.007110454], + ['Pb208',0.016859176]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-30.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s4 = mcdc.surface('plane-z', z=2.8575, bc='interface') +s5 = mcdc.surface('plane-z', z=3.175, bc='interface') +s6 = mcdc.surface('plane-z', z=3.556, bc='interface') +s7 = mcdc.surface('plane-z', z=4.056, bc='interface') +s8 = mcdc.surface('plane-z', z=5.715, bc='interface') +s9 = mcdc.surface('plane-z', z=92.3925, bc='interface') +s10 = mcdc.surface('plane-z', z=94.9325, bc='interface') +s11 = mcdc.surface('plane-z', z=94.996, bc='interface') +s12 = mcdc.surface('plane-z', z=95.8215, bc='interface') +s14 = mcdc.surface('plane-z', z=96.774, bc='interface') +s15 = mcdc.surface('plane-z', z=110.236, bc='vacuum') +s21 = mcdc.surface('plane-x', x=0.0, bc='reflective') +s23 = mcdc.surface('plane-y', y=0.0, bc='reflective') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=70.0, bc='vacuum') +s35 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.64135, bc='interface') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.71755, bc='interface') +s37 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.16204514, bc='interface') +s38 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.04709786, bc='interface') +s39 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.16204514, bc='interface') +s40 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.04709786, bc='interface') +s41 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.16204514, bc='interface') +s42 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.04709786, bc='interface') +s43 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.16204514, bc='interface') +s44 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.04709786, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s21 & +s23 & -s25 & +s1 & -s2, fill=m4) +c2 = mcdc.cell(+s21 & +s23 & -s25 & +s2 & -s4, fill=m5) +c4 = mcdc.cell(+s21 & +s23 & -s25 & +s12 & -s14, fill=m6) +c5 = mcdc.cell(+s21 & +s23 & -s25 & +s14 & -s15, fill=m4) +c21 = mcdc.cell(-s6 & -s36, fill=m3) +c22 = mcdc.cell(+s6 & -s7 & -s35, fill=m2) +c23 = mcdc.cell(+s7 & -s11 & -s35, fill=m1) +c24 = mcdc.cell(+s6 & -s11 & +s35 & -s36, fill=m3) +c25 = mcdc.cell(+s11 & -s36, fill=m3) +c26 = mcdc.cell(-s5 & +s36, fill=m4) +c27 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c28 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c29 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c30 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c31 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c32 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c33 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c34 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c35 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c36 = mcdc.cell(+s8 & -s9 & +s36, fill=m4) +c37 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c38 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c39 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c40 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c41 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c42 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c43 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c44 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c45 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c46 = mcdc.cell(+s10 & +s36, fill=m4) +c51 = mcdc.cell(-s5, fill=m4) +c52 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c53 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c54 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c55 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c56 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44, fill=m4) +c57 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c58 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c59 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c60 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c61 = mcdc.cell(+s8 & -s9, fill=m4) +c62 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c63 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c64 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c65 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c66 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44, fill=m4) +c67 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c68 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c69 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c70 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c71 = mcdc.cell(+s10, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 11 +Lattice11 = mcdc.lattice(x=[-1.10457, 2.20914, 33], y=[-1.10457, 2.20914, 33], \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-34.py b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-34.py new file mode 100644 index 0000000..1bfd6f7 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-34.py @@ -0,0 +1,190 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2-PuO2 Mixture +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8836e-08], + ['Pu239',0.00039462], + ['Pu240',3.3206e-05], + ['Pu242',1.1882e-07], + ['Am241',1.4954e-06], + ['U235',0.00014886], + ['U238',0.020611], + ['O16',0.043779]]) +# Material Name: Natural UO2 Layer +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00014824], + ['U238',0.020525], + ['O16',0.041943]]) +# Material Name: Cladding +m3 = mcdc.material(nuclides=[ + ['Sn112',4.687816e-06], + ['Sn114',3.189648e-06], + ['Sn115',1.643152e-06], + ['Sn116',7.0268912e-05], + ['Sn117',3.7115904e-05], + ['Sn118',0.00011705041599999999], + ['Sn119',4.1513752000000004e-05], + ['Sn120',0.00015745262399999998], + ['Sn122',2.2375864e-05], + ['Sn124',2.7981912e-05], + ['Fe54',5.5902749000000005e-06], + ['Fe56',8.775536068e-05], + ['Fe57',2.02665398e-06], + ['Fe58',2.6971044e-07], + ['Cr50',3.3062408500000004e-06], + ['Cr52',6.375756377000001e-05], + ['Cr53',7.2295959300000005e-06], + ['Cr54',1.7995994500000002e-06], + ['Ni58',2.0651808383999998e-05], + ['Ni60',7.955039615999999e-06], + ['Ni61',3.4580006399999995e-07], + ['Ni62',1.10256192e-06], + ['Ni64',2.80790016e-07], + ['Zr90',0.021928504499999998], + ['Zr91',0.0047820762], + ['Zr92',0.0073095015], + ['Zr94',0.007407529800000001], + ['Zr96',0.001193388]]) +# Material Name: Moderator +# S(a,b): c_H_in_H2O (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.066706], + ['O16',0.033340359213], + ['O17',1.2640787e-05], + ['B10',1.7606e-08], + ['B11',7.1313e-08]]) +# Material Name: 6061 Aluminum +m5 = mcdc.material(nuclides=[ + ['Si28',0.00031917925357600004], + ['Si29',1.6207011812000003e-05], + ['Si30',1.0683734612e-05], + ['Fe54',5.933844e-06], + ['Fe56',9.31486608e-05], + ['Fe57',2.1512088e-06], + ['Fe58',2.862864e-07], + ['Cu63',4.40699865e-05], + ['Cu65',1.96610135e-05], + ['Mn55',2.2115e-05], + ['Mg24',0.0005262163101000001], + ['Mg25',6.6784302e-05], + ['Mg26',7.350938790000001e-05], + ['Cr50',2.7073695000000004e-06], + ['Cr52',5.220892590000001e-05], + ['Cr53',5.9200731000000005e-06], + ['Cr54',1.4736315e-06], + ['Zn64',1.5226473899999998e-05], + ['Zn66',8.587149099999998e-06], + ['Zn67',1.2510667999999998e-06], + ['Zn68',5.713411499999999e-06], + ['Zn70',1.888987e-07], + ['Ti46',2.0934375000000002e-06], + ['Ti47',1.8879000000000002e-06], + ['Ti48',1.8706449999999998e-05], + ['Ti49',1.3727875e-06], + ['Ti50',1.314425e-06], + ['Al27',0.058433]]) +# Material Name: Lead +m6 = mcdc.material(nuclides=[ + ['Pb204',0.000450436], + ['Pb206',0.007753934], + ['Pb207',0.007110454], + ['Pb208',0.016859176]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-30.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s4 = mcdc.surface('plane-z', z=2.8575, bc='interface') +s5 = mcdc.surface('plane-z', z=3.175, bc='interface') +s6 = mcdc.surface('plane-z', z=3.556, bc='interface') +s7 = mcdc.surface('plane-z', z=4.056, bc='interface') +s8 = mcdc.surface('plane-z', z=5.715, bc='interface') +s9 = mcdc.surface('plane-z', z=92.3925, bc='interface') +s10 = mcdc.surface('plane-z', z=94.9325, bc='interface') +s11 = mcdc.surface('plane-z', z=94.996, bc='interface') +s12 = mcdc.surface('plane-z', z=95.8215, bc='interface') +s14 = mcdc.surface('plane-z', z=96.774, bc='interface') +s15 = mcdc.surface('plane-z', z=97.282, bc='vacuum') +s21 = mcdc.surface('plane-x', x=0.0, bc='reflective') +s23 = mcdc.surface('plane-y', y=0.0, bc='reflective') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=60.0, bc='vacuum') +s35 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.64135, bc='interface') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.71755, bc='interface') +s37 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.48174226, bc='interface') +s38 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.03272945, bc='interface') +s39 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.48174226, bc='interface') +s40 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.03272945, bc='interface') +s41 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.48174226, bc='interface') +s42 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.03272945, bc='interface') +s43 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.48174226, bc='interface') +s44 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.03272945, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s21 & +s23 & -s25 & +s1 & -s2, fill=m4) +c2 = mcdc.cell(+s21 & +s23 & -s25 & +s2 & -s4, fill=m5) +c4 = mcdc.cell(+s21 & +s23 & -s25 & +s12 & -s14, fill=m6) +c5 = mcdc.cell(+s21 & +s23 & -s25 & +s14 & -s15, fill=m4) +c21 = mcdc.cell(-s6 & -s36, fill=m3) +c22 = mcdc.cell(+s6 & -s7 & -s35, fill=m2) +c23 = mcdc.cell(+s7 & -s11 & -s35, fill=m1) +c24 = mcdc.cell(+s6 & -s11 & +s35 & -s36, fill=m3) +c25 = mcdc.cell(+s11 & -s36, fill=m3) +c26 = mcdc.cell(-s5 & +s36, fill=m4) +c27 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c28 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c29 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c30 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c31 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c32 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c33 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c34 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c35 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c36 = mcdc.cell(+s8 & -s9 & +s36, fill=m4) +c37 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c38 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c39 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c40 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c41 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c42 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c43 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c44 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c45 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c46 = mcdc.cell(+s10 & +s36, fill=m4) +c51 = mcdc.cell(-s5, fill=m4) +c52 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c53 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c54 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c55 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c56 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44, fill=m4) +c57 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c58 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c59 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c60 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c61 = mcdc.cell(+s8 & -s9, fill=m4) +c62 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c63 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c64 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c65 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c66 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44, fill=m4) +c67 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c68 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c69 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c70 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c71 = mcdc.cell(+s10, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 11 +Lattice11 = mcdc.lattice(x=[-1.257235, 2.51447, 25], y=[-1.257235, 2.51447, 25], \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-35.py b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-35.py new file mode 100644 index 0000000..47a5cea --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/mcdc/mix-comp-therm-002_pnl-35.py @@ -0,0 +1,190 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2-PuO2 Mixture +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8836e-08], + ['Pu239',0.00039462], + ['Pu240',3.3206e-05], + ['Pu242',1.1882e-07], + ['Am241',1.4954e-06], + ['U235',0.00014886], + ['U238',0.020611], + ['O16',0.043779]]) +# Material Name: Natural UO2 Layer +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00014824], + ['U238',0.020525], + ['O16',0.041943]]) +# Material Name: Cladding +m3 = mcdc.material(nuclides=[ + ['Sn112',4.687816e-06], + ['Sn114',3.189648e-06], + ['Sn115',1.643152e-06], + ['Sn116',7.0268912e-05], + ['Sn117',3.7115904e-05], + ['Sn118',0.00011705041599999999], + ['Sn119',4.1513752000000004e-05], + ['Sn120',0.00015745262399999998], + ['Sn122',2.2375864e-05], + ['Sn124',2.7981912e-05], + ['Fe54',5.5902749000000005e-06], + ['Fe56',8.775536068e-05], + ['Fe57',2.02665398e-06], + ['Fe58',2.6971044e-07], + ['Cr50',3.3062408500000004e-06], + ['Cr52',6.375756377000001e-05], + ['Cr53',7.2295959300000005e-06], + ['Cr54',1.7995994500000002e-06], + ['Ni58',2.0651808383999998e-05], + ['Ni60',7.955039615999999e-06], + ['Ni61',3.4580006399999995e-07], + ['Ni62',1.10256192e-06], + ['Ni64',2.80790016e-07], + ['Zr90',0.021928504499999998], + ['Zr91',0.0047820762], + ['Zr92',0.0073095015], + ['Zr94',0.007407529800000001], + ['Zr96',0.001193388]]) +# Material Name: Moderator +# S(a,b): c_H_in_H2O (Not Implemented) +m4 = mcdc.material(nuclides=[ + ['H1',0.066682], + ['O16',0.03339233950499999], + ['O17',1.2660494999999998e-05], + ['B10',8.4597e-06], + ['B11',3.4266e-05]]) +# Material Name: 6061 Aluminum +m5 = mcdc.material(nuclides=[ + ['Si28',0.00031917925357600004], + ['Si29',1.6207011812000003e-05], + ['Si30',1.0683734612e-05], + ['Fe54',5.933844e-06], + ['Fe56',9.31486608e-05], + ['Fe57',2.1512088e-06], + ['Fe58',2.862864e-07], + ['Cu63',4.40699865e-05], + ['Cu65',1.96610135e-05], + ['Mn55',2.2115e-05], + ['Mg24',0.0005262163101000001], + ['Mg25',6.6784302e-05], + ['Mg26',7.350938790000001e-05], + ['Cr50',2.7073695000000004e-06], + ['Cr52',5.220892590000001e-05], + ['Cr53',5.9200731000000005e-06], + ['Cr54',1.4736315e-06], + ['Zn64',1.5226473899999998e-05], + ['Zn66',8.587149099999998e-06], + ['Zn67',1.2510667999999998e-06], + ['Zn68',5.713411499999999e-06], + ['Zn70',1.888987e-07], + ['Ti46',2.0934375000000002e-06], + ['Ti47',1.8879000000000002e-06], + ['Ti48',1.8706449999999998e-05], + ['Ti49',1.3727875e-06], + ['Ti50',1.314425e-06], + ['Al27',0.058433]]) +# Material Name: Lead +m6 = mcdc.material(nuclides=[ + ['Pb204',0.000450436], + ['Pb206',0.007753934], + ['Pb207',0.007110454], + ['Pb208',0.016859176]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-30.0, bc='vacuum') +s2 = mcdc.surface('plane-z', z=0.0, bc='interface') +s4 = mcdc.surface('plane-z', z=2.8575, bc='interface') +s5 = mcdc.surface('plane-z', z=3.175, bc='interface') +s6 = mcdc.surface('plane-z', z=3.556, bc='interface') +s7 = mcdc.surface('plane-z', z=4.056, bc='interface') +s8 = mcdc.surface('plane-z', z=5.715, bc='interface') +s9 = mcdc.surface('plane-z', z=92.3925, bc='interface') +s10 = mcdc.surface('plane-z', z=94.9325, bc='interface') +s11 = mcdc.surface('plane-z', z=94.996, bc='interface') +s12 = mcdc.surface('plane-z', z=95.8215, bc='interface') +s14 = mcdc.surface('plane-z', z=96.774, bc='interface') +s15 = mcdc.surface('plane-z', z=110.236, bc='vacuum') +s21 = mcdc.surface('plane-x', x=0.0, bc='reflective') +s23 = mcdc.surface('plane-y', y=0.0, bc='reflective') +s25 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=70.0, bc='vacuum') +s35 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.64135, bc='interface') +s36 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.71755, bc='interface') +s37 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.48174226, bc='interface') +s38 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=1.03272945, bc='interface') +s39 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.48174226, bc='interface') +s40 = mcdc.surface('plane', A=1.0, B=-1.0, C=0.0, D=-1.03272945, bc='interface') +s41 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.48174226, bc='interface') +s42 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=-1.03272945, bc='interface') +s43 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.48174226, bc='interface') +s44 = mcdc.surface('plane', A=1.0, B=1.0, C=0.0, D=1.03272945, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s21 & +s23 & -s25 & +s1 & -s2, fill=m4) +c2 = mcdc.cell(+s21 & +s23 & -s25 & +s2 & -s4, fill=m5) +c4 = mcdc.cell(+s21 & +s23 & -s25 & +s12 & -s14, fill=m6) +c5 = mcdc.cell(+s21 & +s23 & -s25 & +s14 & -s15, fill=m4) +c21 = mcdc.cell(-s6 & -s36, fill=m3) +c22 = mcdc.cell(+s6 & -s7 & -s35, fill=m2) +c23 = mcdc.cell(+s7 & -s11 & -s35, fill=m1) +c24 = mcdc.cell(+s6 & -s11 & +s35 & -s36, fill=m3) +c25 = mcdc.cell(+s11 & -s36, fill=m3) +c26 = mcdc.cell(-s5 & +s36, fill=m4) +c27 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c28 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c29 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c30 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c31 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c32 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c33 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c34 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c35 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c36 = mcdc.cell(+s8 & -s9 & +s36, fill=m4) +c37 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c38 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c39 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c40 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c41 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44 & +s36, fill=m4) +c42 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c43 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c44 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c45 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c46 = mcdc.cell(+s10 & +s36, fill=m4) +c51 = mcdc.cell(-s5, fill=m4) +c52 = mcdc.cell(+s5 & -s8 & -s37 & +s38, fill=m5) +c53 = mcdc.cell(+s5 & -s8 & +s39 & -s40, fill=m5) +c54 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s41 & -s42, fill=m5) +c55 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & -s43 & +s44, fill=m5) +c56 = mcdc.cell(+s5 & -s8 & -s38 & +s40 & +s42 & -s44, fill=m4) +c57 = mcdc.cell(+s5 & -s8 & +s37, fill=m4) +c58 = mcdc.cell(+s5 & -s8 & -s39, fill=m4) +c59 = mcdc.cell(+s5 & -s8 & -s41, fill=m4) +c60 = mcdc.cell(+s5 & -s8 & +s43, fill=m4) +c61 = mcdc.cell(+s8 & -s9, fill=m4) +c62 = mcdc.cell(+s9 & -s10 & -s37 & +s38, fill=m5) +c63 = mcdc.cell(+s9 & -s10 & +s39 & -s40, fill=m5) +c64 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s41 & -s42, fill=m5) +c65 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & -s43 & +s44, fill=m5) +c66 = mcdc.cell(+s9 & -s10 & -s38 & +s40 & +s42 & -s44, fill=m4) +c67 = mcdc.cell(+s9 & -s10 & +s37, fill=m4) +c68 = mcdc.cell(+s9 & -s10 & -s39, fill=m4) +c69 = mcdc.cell(+s9 & -s10 & -s41, fill=m4) +c70 = mcdc.cell(+s9 & -s10 & +s43, fill=m4) +c71 = mcdc.cell(+s10, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 11 +Lattice11 = mcdc.lattice(x=[-1.257235, 2.51447, 29], y=[-1.257235, 2.51447, 29], \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/generate_materials.py b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/generate_materials.py new file mode 100644 index 0000000..126e0d1 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2-PuO2 Mixture" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8836e-08) +mat.add_nuclide('Pu239', 3.9462e-04) +mat.add_nuclide('Pu240', 3.3206e-05) +mat.add_nuclide('Pu241', 1.6081e-06) +mat.add_nuclide('Pu242', 1.1882e-07) +mat.add_nuclide('Am241', 1.4954e-06) +mat.add_nuclide('U234', 1.2458e-06) +mat.add_nuclide('U235', 1.4886e-04) +mat.add_nuclide('U236', 2.0936e-09) +mat.add_nuclide('U238', 2.0611e-02) +mat.add_nuclide('O16', 4.3779e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural UO2 Layer" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2406e-06) +mat.add_nuclide('U235', 1.4824e-04) +mat.add_nuclide('U236', 2.0848e-09) +mat.add_nuclide('U238', 2.0525e-02) +mat.add_nuclide('O16', 4.1943e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cladding" +mat.set_density('sum') +mat.add_element('Sn', 4.8328e-04) +mat.add_element('Fe', 9.5642e-05) +mat.add_element('Cr', 7.6093e-05) +mat.add_element('Ni', 3.0336e-05) +mat.add_element('Zr', 4.2621e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Moderator" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6706e-02) +mat.add_element('O', 3.3353e-02) +mat.add_nuclide('B10', 1.8706e-08) +mat.add_nuclide('B11', 7.5770e-08) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "6061 Aluminum" +mat.set_density('sum') +mat.add_element('Si', 3.4607e-04) +mat.add_element('Fe', 1.0152e-04) +mat.add_element('Cu', 6.3731e-05) +mat.add_element('Mn', 2.2115e-05) +mat.add_element('Mg', 6.6651e-04) +mat.add_element('Cr', 6.2310e-05) +mat.add_element('Zn', 3.0967e-05) +mat.add_element('Ti', 2.5375e-05) +mat.add_element('Al', 5.8433e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/geometry.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/geometry.xml new file mode 100644 index 0000000..78ce374 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/geometry.xml @@ -0,0 +1,120 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 29 29 + -0.889 -0.889 + 1.778 1.778 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/materials.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/materials.xml new file mode 100644 index 0000000..7cbfabf --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/materials.xml @@ -0,0 +1,103 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/plots.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/plots.xml new file mode 100644 index 0000000..e44b909 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/plots.xml @@ -0,0 +1,20 @@ + + + + + + + xy + 25. 25. 4.5 + 50. 50. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/settings.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/settings.xml new file mode 100644 index 0000000..ba34cd1 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-30/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + 0. 0. 3.5560 + 21.336 21.336 94.9960 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/generate_materials.py b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/generate_materials.py new file mode 100644 index 0000000..3467e97 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2-PuO2 Mixture" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8836e-08) +mat.add_nuclide('Pu239', 3.9462e-04) +mat.add_nuclide('Pu240', 3.3206e-05) +mat.add_nuclide('Pu241', 1.6081e-06) +mat.add_nuclide('Pu242', 1.1882e-07) +mat.add_nuclide('Am241', 1.4954e-06) +mat.add_nuclide('U234', 1.2458e-06) +mat.add_nuclide('U235', 1.4886e-04) +mat.add_nuclide('U236', 2.0936e-09) +mat.add_nuclide('U238', 2.0611e-02) +mat.add_nuclide('O16', 4.3779e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural UO2 Layer" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2406e-06) +mat.add_nuclide('U235', 1.4824e-04) +mat.add_nuclide('U236', 2.0848e-09) +mat.add_nuclide('U238', 2.0525e-02) +mat.add_nuclide('O16', 4.1943e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cladding" +mat.set_density('sum') +mat.add_element('Sn', 4.8328e-04) +mat.add_element('Fe', 9.5642e-05) +mat.add_element('Cr', 7.6093e-05) +mat.add_element('Ni', 3.0336e-05) +mat.add_element('Zr', 4.2621e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Moderator" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6685e-02) +mat.add_element('O', 3.3400e-02) +mat.add_nuclide('B10', 7.5838e-06) +mat.add_nuclide('B11', 3.0718e-05) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "6061 Aluminum" +mat.set_density('sum') +mat.add_element('Si', 3.4607e-04) +mat.add_element('Fe', 1.0152e-04) +mat.add_element('Cu', 6.3731e-05) +mat.add_element('Mn', 2.2115e-05) +mat.add_element('Mg', 6.6651e-04) +mat.add_element('Cr', 6.2310e-05) +mat.add_element('Zn', 3.0967e-05) +mat.add_element('Ti', 2.5375e-05) +mat.add_element('Al', 5.8433e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/geometry.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/geometry.xml new file mode 100644 index 0000000..b3a463e --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/geometry.xml @@ -0,0 +1,126 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 35 35 + -0.889 -0.889 + 1.778 1.778 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/materials.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/materials.xml new file mode 100644 index 0000000..4826950 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/materials.xml @@ -0,0 +1,103 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/plots.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/plots.xml new file mode 100644 index 0000000..6fba4d0 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/plots.xml @@ -0,0 +1,20 @@ + + + + + + + xy + 30. 30. 4.5 + 60. 60. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/settings.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/settings.xml new file mode 100644 index 0000000..1d91733 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-31/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + 0. 0. 3.5560 + 28.448 28.448 94.9960 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/generate_materials.py b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/generate_materials.py new file mode 100644 index 0000000..0146fcf --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2-PuO2 Mixture" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8836e-08) +mat.add_nuclide('Pu239', 3.9462e-04) +mat.add_nuclide('Pu240', 3.3206e-05) +mat.add_nuclide('Pu241', 1.6081e-06) +mat.add_nuclide('Pu242', 1.1882e-07) +mat.add_nuclide('Am241', 1.4954e-06) +mat.add_nuclide('U234', 1.2458e-06) +mat.add_nuclide('U235', 1.4886e-04) +mat.add_nuclide('U236', 2.0936e-09) +mat.add_nuclide('U238', 2.0611e-02) +mat.add_nuclide('O16', 4.3779e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural UO2 Layer" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2406e-06) +mat.add_nuclide('U235', 1.4824e-04) +mat.add_nuclide('U236', 2.0848e-09) +mat.add_nuclide('U238', 2.0525e-02) +mat.add_nuclide('O16', 4.1943e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cladding" +mat.set_density('sum') +mat.add_element('Sn', 4.8328e-04) +mat.add_element('Fe', 9.5642e-05) +mat.add_element('Cr', 7.6093e-05) +mat.add_element('Ni', 3.0336e-05) +mat.add_element('Zr', 4.2621e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Moderator" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6706e-02) +mat.add_element('O', 3.3353e-02) +mat.add_nuclide('B10', 9.9034e-09) +mat.add_nuclide('B11', 4.0114e-08) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "6061 Aluminum" +mat.set_density('sum') +mat.add_element('Si', 3.4607e-04) +mat.add_element('Fe', 1.0152e-04) +mat.add_element('Cu', 6.3731e-05) +mat.add_element('Mn', 2.2115e-05) +mat.add_element('Mg', 6.6651e-04) +mat.add_element('Cr', 6.2310e-05) +mat.add_element('Zn', 3.0967e-05) +mat.add_element('Ti', 2.5375e-05) +mat.add_element('Al', 5.8433e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/geometry.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/geometry.xml new file mode 100644 index 0000000..12b6e10 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/geometry.xml @@ -0,0 +1,138 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 28 28 + -1.10457 -1.10457 + 2.20914 2.20914 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/materials.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/materials.xml new file mode 100644 index 0000000..6c32fb4 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/materials.xml @@ -0,0 +1,103 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/plots.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/plots.xml new file mode 100644 index 0000000..bd4882e --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/plots.xml @@ -0,0 +1,20 @@ + + + + + + + xy + 30. 30. 4.5 + 60. 60. + 2000 2000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/settings.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/settings.xml new file mode 100644 index 0000000..f4e5ddd --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-32/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + 0. 0. 3.5560 + 19.88226 19.88226 94.9960 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/generate_materials.py b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/generate_materials.py new file mode 100644 index 0000000..13370fd --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2-PuO2 Mixture" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8836e-08) +mat.add_nuclide('Pu239', 3.9462e-04) +mat.add_nuclide('Pu240', 3.3206e-05) +mat.add_nuclide('Pu241', 1.6081e-06) +mat.add_nuclide('Pu242', 1.1882e-07) +mat.add_nuclide('Am241', 1.4954e-06) +mat.add_nuclide('U234', 1.2458e-06) +mat.add_nuclide('U235', 1.4886e-04) +mat.add_nuclide('U236', 2.0936e-09) +mat.add_nuclide('U238', 2.0611e-02) +mat.add_nuclide('O16', 4.3779e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural UO2 Layer" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2406e-06) +mat.add_nuclide('U235', 1.4824e-04) +mat.add_nuclide('U236', 2.0848e-09) +mat.add_nuclide('U238', 2.0525e-02) +mat.add_nuclide('O16', 4.1943e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cladding" +mat.set_density('sum') +mat.add_element('Sn', 4.8328e-04) +mat.add_element('Fe', 9.5642e-05) +mat.add_element('Cr', 7.6093e-05) +mat.add_element('Ni', 3.0336e-05) +mat.add_element('Zr', 4.2621e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Moderator" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6672e-02) +mat.add_element('O', 3.3427e-02) +mat.add_nuclide('B10', 1.2034e-5) +mat.add_nuclide('B11', 4.8746e-5) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "6061 Aluminum" +mat.set_density('sum') +mat.add_element('Si', 3.4607e-04) +mat.add_element('Fe', 1.0152e-04) +mat.add_element('Cu', 6.3731e-05) +mat.add_element('Mn', 2.2115e-05) +mat.add_element('Mg', 6.6651e-04) +mat.add_element('Cr', 6.2310e-05) +mat.add_element('Zn', 3.0967e-05) +mat.add_element('Ti', 2.5375e-05) +mat.add_element('Al', 5.8433e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/geometry.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/geometry.xml new file mode 100644 index 0000000..d6cca17 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/geometry.xml @@ -0,0 +1,143 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 33 33 + -1.10457 -1.10457 + 2.20914 2.20914 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/materials.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/materials.xml new file mode 100644 index 0000000..9ca770d --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/materials.xml @@ -0,0 +1,103 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/plots.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/plots.xml new file mode 100644 index 0000000..c91dc9c --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/plots.xml @@ -0,0 +1,20 @@ + + + + + + + xy + 35. 35. 4.5 + 70. 70. + 2000 2000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/settings.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/settings.xml new file mode 100644 index 0000000..20d36d5 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-33/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + 0. 0. 3.5560 + 35.34624 35.34624 94.9960 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/generate_materials.py b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/generate_materials.py new file mode 100644 index 0000000..053d588 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2-PuO2 Mixture" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8836e-08) +mat.add_nuclide('Pu239', 3.9462e-04) +mat.add_nuclide('Pu240', 3.3206e-05) +mat.add_nuclide('Pu241', 1.6081e-06) +mat.add_nuclide('Pu242', 1.1882e-07) +mat.add_nuclide('Am241', 1.4954e-06) +mat.add_nuclide('U234', 1.2458e-06) +mat.add_nuclide('U235', 1.4886e-04) +mat.add_nuclide('U236', 2.0936e-09) +mat.add_nuclide('U238', 2.0611e-02) +mat.add_nuclide('O16', 4.3779e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural UO2 Layer" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2406e-06) +mat.add_nuclide('U235', 1.4824e-04) +mat.add_nuclide('U236', 2.0848e-09) +mat.add_nuclide('U238', 2.0525e-02) +mat.add_nuclide('O16', 4.1943e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cladding" +mat.set_density('sum') +mat.add_element('Sn', 4.8328e-04) +mat.add_element('Fe', 9.5642e-05) +mat.add_element('Cr', 7.6093e-05) +mat.add_element('Ni', 3.0336e-05) +mat.add_element('Zr', 4.2621e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Moderator" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6706e-02) +mat.add_element('O', 3.3353e-02) +mat.add_nuclide('B10', 1.7606e-08) +mat.add_nuclide('B11', 7.1313e-08) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "6061 Aluminum" +mat.set_density('sum') +mat.add_element('Si', 3.4607e-04) +mat.add_element('Fe', 1.0152e-04) +mat.add_element('Cu', 6.3731e-05) +mat.add_element('Mn', 2.2115e-05) +mat.add_element('Mg', 6.6651e-04) +mat.add_element('Cr', 6.2310e-05) +mat.add_element('Zn', 3.0967e-05) +mat.add_element('Ti', 2.5375e-05) +mat.add_element('Al', 5.8433e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/geometry.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/geometry.xml new file mode 100644 index 0000000..257e426 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/geometry.xml @@ -0,0 +1,135 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 25 25 + -1.257235 -1.257235 + 2.51447 2.51447 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/materials.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/materials.xml new file mode 100644 index 0000000..72ecbac --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/materials.xml @@ -0,0 +1,103 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/plots.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/plots.xml new file mode 100644 index 0000000..4813877 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/plots.xml @@ -0,0 +1,20 @@ + + + + + + + xy + 30. 30. 4.5 + 60. 60. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/settings.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/settings.xml new file mode 100644 index 0000000..bd2fb6b --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-34/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + 0. 0. 3.5560 + 22.63023 22.63023 94.9960 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/generate_materials.py b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/generate_materials.py new file mode 100644 index 0000000..d907580 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2-PuO2 Mixture" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8836e-08) +mat.add_nuclide('Pu239', 3.9462e-04) +mat.add_nuclide('Pu240', 3.3206e-05) +mat.add_nuclide('Pu241', 1.6081e-06) +mat.add_nuclide('Pu242', 1.1882e-07) +mat.add_nuclide('Am241', 1.4954e-06) +mat.add_nuclide('U234', 1.2458e-06) +mat.add_nuclide('U235', 1.4886e-04) +mat.add_nuclide('U236', 2.0936e-09) +mat.add_nuclide('U238', 2.0611e-02) +mat.add_nuclide('O16', 4.3779e-02) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural UO2 Layer" +mat.set_density('sum') +mat.add_nuclide('U234', 1.2406e-06) +mat.add_nuclide('U235', 1.4824e-04) +mat.add_nuclide('U236', 2.0848e-09) +mat.add_nuclide('U238', 2.0525e-02) +mat.add_nuclide('O16', 4.1943e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cladding" +mat.set_density('sum') +mat.add_element('Sn', 4.8328e-04) +mat.add_element('Fe', 9.5642e-05) +mat.add_element('Cr', 7.6093e-05) +mat.add_element('Ni', 3.0336e-05) +mat.add_element('Zr', 4.2621e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Moderator" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6682e-02) +mat.add_element('O', 3.3405e-02) +mat.add_nuclide('B10', 8.4597e-06) +mat.add_nuclide('B11', 3.4266e-05) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "6061 Aluminum" +mat.set_density('sum') +mat.add_element('Si', 3.4607e-04) +mat.add_element('Fe', 1.0152e-04) +mat.add_element('Cu', 6.3731e-05) +mat.add_element('Mn', 2.2115e-05) +mat.add_element('Mg', 6.6651e-04) +mat.add_element('Cr', 6.2310e-05) +mat.add_element('Zn', 3.0967e-05) +mat.add_element('Ti', 2.5375e-05) +mat.add_element('Al', 5.8433e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead" +mat.set_density('sum') +mat.add_element('Pb', 3.2174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/geometry.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/geometry.xml new file mode 100644 index 0000000..42741f0 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/geometry.xml @@ -0,0 +1,139 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 29 29 + -1.257235 -1.257235 + 2.51447 2.51447 + + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/materials.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/materials.xml new file mode 100644 index 0000000..0e6aab5 --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/materials.xml @@ -0,0 +1,103 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/plots.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/plots.xml new file mode 100644 index 0000000..3a8a8bb --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/plots.xml @@ -0,0 +1,20 @@ + + + + + + + xy + 35. 35. 4.5 + 70. 70. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/settings.xml b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/settings.xml new file mode 100644 index 0000000..35211ac --- /dev/null +++ b/icsbep/openmc/mix-comp-therm-002/openmc/pnl-35/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + 0. 0. 3.5560 + 37.71705 37.71705 94.9960 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-001/mcdc/mix-met-fast-001.py b/icsbep/openmc/mix-met-fast-001/mcdc/mix-met-fast-001.py new file mode 100644 index 0000000..1b3acca --- /dev/null +++ b/icsbep/openmc/mix-met-fast-001/mcdc/mix-met-fast-001.py @@ -0,0 +1,47 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037291], + ['Pu240',0.0019277], + ['Ga69',0.00081915], + ['Ga71',0.00054365]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.044892], + ['U238',0.003234]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0419, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.7056, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-001/openmc/geometry.xml b/icsbep/openmc/mix-met-fast-001/openmc/geometry.xml new file mode 100644 index 0000000..2cd52d1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-001/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-001/openmc/materials.xml b/icsbep/openmc/mix-met-fast-001/openmc/materials.xml new file mode 100644 index 0000000..7e04349 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-001/openmc/materials.xml @@ -0,0 +1,28 @@ + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-001/openmc/settings.xml b/icsbep/openmc/mix-met-fast-001/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/mix-met-fast-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-003/mcdc/mix-met-fast-003.py b/icsbep/openmc/mix-met-fast-003/mcdc/mix-met-fast-003.py new file mode 100644 index 0000000..9a8fb50 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-003/mcdc/mix-met-fast-003.py @@ -0,0 +1,132 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.033928], + ['Pu240',0.0035031999999999997], + ['Ga69',0.001328627232], + ['Ga71',0.0008817727679999999], + ['C0',0.00030244], + ['Fe54',1.9009693499999997e-05], + ['Fe56',0.0002984115342], + ['Fe57',6.8916237e-06], + ['Fe58',9.171486000000001e-07], + ['W180',8.891279999999999e-08], + ['W182',1.963491e-05], + ['W183',1.06028514e-05], + ['W184',2.27024016e-05], + ['W186',2.10649242e-05], + ['Ni58',0.0009711850554000001], + ['Ni60',0.0003740987446], + ['Ni61',1.62618134e-05], + ['Ni62',5.1849777e-05], + ['Ni64',1.3204609600000002e-05]]) +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.041081], + ['U238',0.0041002], + ['C0',0.0003865], + ['Fe54',8.7832815e-06], + ['Fe56',0.0001378787358], + ['Fe57',3.1842213000000005e-06], + ['Fe58',4.2376140000000003e-07], + ['W180',1.4794799999999999e-08], + ['W182',3.267185e-06], + ['W183',1.7642799000000003e-06], + ['W184',3.7776056000000005e-06], + ['W186',3.5051346999999994e-06], + ['Cu63',0.00050912379], + ['Cu65',0.00022713621000000002], + ['Ni58',0.00023258472884999997], + ['Ni60',8.959122115e-05], + ['Ni61',3.8944683499999995e-06], + ['Ni62',1.2417269250000001e-05], + ['Ni64',3.1623124e-06]]) +# Material Name: Iron +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Copper +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +# Material Name: Duralumin +m5 = mcdc.material(nuclides=[ + ['Al27',0.058077], + ['Mg24',0.000815721732], + ['Mg25',0.00010352663999999999], + ['Mg26',0.00011395162799999999], + ['Mn55',0.00018284], + ['Cu63',0.0007834003500000001], + ['Cu65',0.00034949965000000003]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.0, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=5.5, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 1.225], radius=5.35, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 1.225], radius=7.55, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.7, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=1.025, bc='interface') +s12 = mcdc.surface('plane-z', z=1.225, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.5, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s15 = mcdc.surface('cylinder-y', center=[0.0, 0.0], radius=0.6, bc='interface') +s16 = mcdc.surface('cylinder-y', center=[0.0, 1.225], radius=0.6, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.0, bc='vacuum') +s18 = mcdc.surface('plane-z', z=-14.7, bc='vacuum') +s19 = mcdc.surface('plane-z', z=9.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s5, fill=m1) +c3 = mcdc.cell(+s5 & -s6 & +s12, fill=mvoid) +c4 = mcdc.cell(+s5 & -s2 & +s11 & -s12, fill=mvoid) +c5 = mcdc.cell(+s5 & -s7 & -s10 & +s15, fill=m2) +c6 = mcdc.cell(+s3 & +s6 & -s8 & +s12 & +s16, fill=m2) +c7 = mcdc.cell(+s5 & -s7 & -s10 & -s15, fill=mvoid) +c8 = mcdc.cell(+s6 & -s8 & +s12 & -s16, fill=mvoid) +c9 = mcdc.cell(+s5 & +s10 & -s11 & -s17, fill=mvoid) +c10 = mcdc.cell(+s2 & +s11 & -s12 & -s17, fill=m5) +c11 = mcdc.cell(+s7 & -s10 & +s13 & -s17 & +s18, fill=mvoid) +c12 = mcdc.cell(+s8 & +s12 & -s17 & -s19, fill=mvoid) +c13 = mcdc.cell(+s7 & -s9 & -s13 & -s10, fill=m4) +c14 = mcdc.cell(+s9 & -s10 & -s14 & +s18, fill=m3) +c15 = mcdc.cell(+s9 & -s10 & -s13 & +s14 & +s18, fill=mvoid) +c16 = mcdc.cell(-s3 & +s6 & -s8 & +s12, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-003/openmc/generate_materials.py b/icsbep/openmc/mix-met-fast-003/openmc/generate_materials.py new file mode 100644 index 0000000..7d528db --- /dev/null +++ b/icsbep/openmc/mix-met-fast-003/openmc/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.3928e-02) +mat.add_nuclide('Pu240', 3.5032e-03) +mat.add_nuclide('Pu241', 3.9158e-04) +mat.add_element('Ga', 2.2104e-03) +mat.add_element('C', 3.0244e-04) +mat.add_element('Fe', 3.2523e-04) +mat.add_element('W', 7.4094e-05) +mat.add_element('Ni', 1.4266e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.1081e-02) +mat.add_nuclide('U238', 4.1002e-03) +mat.add_nuclide('U234', 5.2253e-04) +mat.add_nuclide('U236', 8.8981e-05) +mat.add_element('C', 3.8650e-04) +mat.add_element('Fe', 1.5027e-04) +mat.add_element('W', 1.2329e-05) +mat.add_element('Cu', 7.3626e-04) +mat.add_element('Ni', 3.4165e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Iron" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Copper" +mat.set_density('sum') +mat.add_element('Cu', 8.2365e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Duralumin" +mat.set_density('sum') +mat.add_element('Al', 5.8077e-02) +mat.add_element('Mg', 1.0332e-03) +mat.add_element('Mn', 1.8284e-04) +mat.add_element('Cu', 1.1329e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-003/openmc/geometry.xml b/icsbep/openmc/mix-met-fast-003/openmc/geometry.xml new file mode 100644 index 0000000..dea2816 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-003/openmc/geometry.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-003/openmc/materials.xml b/icsbep/openmc/mix-met-fast-003/openmc/materials.xml new file mode 100644 index 0000000..cdd2ddd --- /dev/null +++ b/icsbep/openmc/mix-met-fast-003/openmc/materials.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-003/openmc/plots.xml b/icsbep/openmc/mix-met-fast-003/openmc/plots.xml new file mode 100644 index 0000000..dc49645 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-003/openmc/plots.xml @@ -0,0 +1,20 @@ + + + + + + + yz + 0. 0. 0. + 30. 30. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-003/openmc/settings.xml b/icsbep/openmc/mix-met-fast-003/openmc/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-003/openmc/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-1.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-1.py new file mode 100644 index 0000000..e0b890d --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-1.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.1298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.8736, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=23.8736, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-10.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-10.py new file mode 100644 index 0000000..e9f29db --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-10.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6789, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.7789, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-11.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-11.py new file mode 100644 index 0000000..dc046ae --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-11.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.1655, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.0455, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-12.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-12.py new file mode 100644 index 0000000..67f6c28 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-12.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.929, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.699, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-13.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-13.py new file mode 100644 index 0000000..47086e3 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-13.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5354, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.2054, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-14.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-14.py new file mode 100644 index 0000000..15ab37b --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-14.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.6537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.869, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.069, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-15.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-15.py new file mode 100644 index 0000000..0a966e2 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-15.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.6537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0637, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=12.4337, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-16.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-16.py new file mode 100644 index 0000000..03dce71 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-16.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.6537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6743, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.2943, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-17.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-17.py new file mode 100644 index 0000000..0d46e90 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-17.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.6537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.1613, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.0613, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-18.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-18.py new file mode 100644 index 0000000..54db284 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-18.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.6537, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.926, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.156, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-19.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-19.py new file mode 100644 index 0000000..257577b --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-19.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.8673, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6732, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.2432, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-2.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-2.py new file mode 100644 index 0000000..254189c --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-2.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.1298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0681, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.2681, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-20.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-20.py new file mode 100644 index 0000000..0095e64 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-20.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.8673, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.6104, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.2504, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-21.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-21.py new file mode 100644 index 0000000..8e363ea --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-21.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.8673, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.9253, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5823, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-22.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-22.py new file mode 100644 index 0000000..b6da518 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-22.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0674, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6772, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.3372, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-23.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-23.py new file mode 100644 index 0000000..1a8f802 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-23.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0674, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.1636, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.6336, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-3.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-3.py new file mode 100644 index 0000000..b75be24 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-3.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.1298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.6777, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.3477, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-4.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-4.py new file mode 100644 index 0000000..73156df --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-4.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.1298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.1639, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.7639, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-5.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-5.py new file mode 100644 index 0000000..7a9dc16 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-5.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.1298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.928, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.668, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-6.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-6.py new file mode 100644 index 0000000..0d7fb3c --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-6.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.1298, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.535, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.895, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-7.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-7.py new file mode 100644 index 0000000..48e0c44 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-7.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.6611, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.9211, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-8.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-8.py new file mode 100644 index 0000000..4619128 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-8.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.8753, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.0453, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-9.py b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-9.py new file mode 100644 index 0000000..3e21f66 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/mcdc/mix-met-fast-007_case-9.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pu core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.045536], + ['Pu240',0.0027719], +# Material Name: HEU +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044401], + ['U238',0.0032137]]) +# Material Name: Beryllium +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12295]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.417, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.0697, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.8497, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-1/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-1/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-1/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-1/geometry.xml new file mode 100644 index 0000000..efc1f40 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-1/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-1/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-1/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-1/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-1/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-10/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-10/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-10/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-10/geometry.xml new file mode 100644 index 0000000..586d336 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-10/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-10/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-10/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-10/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-10/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-10/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-10/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-11/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-11/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-11/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-11/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-11/geometry.xml new file mode 100644 index 0000000..ad296d8 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-11/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-11/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-11/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-11/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-11/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-11/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-11/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-12/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-12/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-12/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-12/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-12/geometry.xml new file mode 100644 index 0000000..46e15b3 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-12/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-12/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-12/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-12/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-12/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-12/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-12/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-13/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-13/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-13/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-13/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-13/geometry.xml new file mode 100644 index 0000000..4eb2df8 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-13/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-13/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-13/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-13/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-13/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-13/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-13/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-14/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-14/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-14/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-14/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-14/geometry.xml new file mode 100644 index 0000000..d01dd1b --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-14/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-14/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-14/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-14/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-14/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-14/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-14/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-15/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-15/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-15/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-15/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-15/geometry.xml new file mode 100644 index 0000000..66cc9b6 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-15/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-15/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-15/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-15/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-15/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-15/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-15/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-16/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-16/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-16/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-16/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-16/geometry.xml new file mode 100644 index 0000000..a165f34 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-16/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-16/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-16/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-16/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-16/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-16/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-16/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-17/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-17/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-17/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-17/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-17/geometry.xml new file mode 100644 index 0000000..9c854ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-17/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-17/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-17/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-17/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-17/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-17/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-17/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-18/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-18/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-18/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-18/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-18/geometry.xml new file mode 100644 index 0000000..16e5e85 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-18/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-18/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-18/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-18/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-18/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-18/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-18/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-19/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-19/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-19/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-19/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-19/geometry.xml new file mode 100644 index 0000000..cfc68eb --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-19/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-19/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-19/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-19/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-19/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-19/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-19/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-2/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-2/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-2/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-2/geometry.xml new file mode 100644 index 0000000..4b08971 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-2/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-2/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-2/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-2/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-2/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-20/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-20/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-20/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-20/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-20/geometry.xml new file mode 100644 index 0000000..cba6271 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-20/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-20/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-20/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-20/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-20/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-20/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-20/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-21/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-21/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-21/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-21/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-21/geometry.xml new file mode 100644 index 0000000..781c669 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-21/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-21/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-21/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-21/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-21/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-21/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-21/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-22/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-22/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-22/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-22/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-22/geometry.xml new file mode 100644 index 0000000..396174e --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-22/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-22/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-22/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-22/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-22/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-22/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-22/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-23/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-23/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-23/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-23/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-23/geometry.xml new file mode 100644 index 0000000..a886a3a --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-23/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-23/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-23/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-23/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-23/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-23/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-23/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-3/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-3/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-3/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-3/geometry.xml new file mode 100644 index 0000000..b4f541f --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-3/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-3/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-3/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-3/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-3/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-4/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-4/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-4/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-4/geometry.xml new file mode 100644 index 0000000..ebfb73c --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-4/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-4/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-4/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-4/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-4/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-4/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-5/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-5/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-5/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-5/geometry.xml new file mode 100644 index 0000000..d00b9a4 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-5/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-5/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-5/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-5/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-5/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-5/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-6/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-6/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-6/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-6/geometry.xml new file mode 100644 index 0000000..fd41b00 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-6/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-6/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-6/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-6/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-6/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-6/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-7/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-7/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-7/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-7/geometry.xml new file mode 100644 index 0000000..49ade2e --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-7/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-7/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-7/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-7/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-7/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-7/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-8/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-8/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-8/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-8/geometry.xml new file mode 100644 index 0000000..2a7a01d --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-8/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-8/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-8/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-8/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-8/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-8/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-9/generate_materials.py b/icsbep/openmc/mix-met-fast-007/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..767cec1 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-9/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pu core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.5536e-02) +mat.add_nuclide('Pu240', 2.7719e-03) +mat.add_nuclide('Pu241', 1.7313e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('U235', 4.4401e-02) +mat.add_nuclide('U238', 3.2137e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Beryllium" +mat.set_density('sum') +mat.add_element('Be', 1.2295e-01) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-9/geometry.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-9/geometry.xml new file mode 100644 index 0000000..425d26f --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-9/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-9/materials.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-9/materials.xml new file mode 100644 index 0000000..b6f39ac --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-9/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-007/openmc/case-9/settings.xml b/icsbep/openmc/mix-met-fast-007/openmc/case-9/settings.xml new file mode 100644 index 0000000..c333595 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-007/openmc/case-9/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-fast-008/mcdc/mix-met-fast-008_8h.py b/icsbep/openmc/mix-met-fast-008/mcdc/mix-met-fast-008_8h.py new file mode 100644 index 0000000..1400485 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-008/mcdc/mix-met-fast-008_8h.py @@ -0,0 +1,142 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Enriched U metal (37.5 w/o) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U235',0.01773], + ['U238',0.028957], + ['C0',0.00018452], + ['O16',0.00034617874851], + ['O17',1.3125149e-07], + ['Fe54',3.47935315e-06], + ['Fe56',5.4618403580000004e-05], + ['Fe57',1.26137713e-06], + ['Fe58',1.6786614e-07], + ['Al27',4.107e-05], + ['H1',4.397115086628e-05], + ['H2',6.84913372e-09], + ['Si28',3.639014254080001e-05], + ['Si29',1.8477876096000002e-06], + ['Si30',1.2180698496e-06]]) +# Material Name: Natural U metal +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00033316], + ['U238',0.045948], + ['C0',0.00049205], + ['Fe54',6.1857635e-06], + ['Fe56',9.71032582e-05], + ['Fe57',2.2425377e-06], + ['Fe58',2.9844059999999997e-07], + ['H1',4.397115086628e-05], + ['H2',6.84913372e-09], + ['Si28',0.00019407891562400005], + ['Si29',9.854773588e-06], + ['Si30',6.496310788e-06]]) +# Material Name: Sheath +m3 = mcdc.material(nuclides=[ + ['C0',0.00077829], + ['Fe54',0.0033096728000000003], + ['Fe56',0.05195478496], + ['Fe57',0.00119986256], + ['Fe58',0.00015967968], + ['Cr50',0.0006998491500000002], + ['Cr52',0.01349589423], + ['Cr53',0.00153032607], + ['Cr54',0.00038093055], + ['Cu63',5.10693495e-05], + ['Cu65',2.2783650499999998e-05], + ['Mo100',1.4260344e-05], + ['Mo92',2.1438811500000004e-05], + ['Mo94',1.34451745e-05], + ['Mo95',2.3230135500000004e-05], + ['Mo96',2.44009355e-05], + ['Mo97',1.4023257e-05], + ['Mo98',3.5551342e-05], + ['Mn55',0.0011918], + ['Ni58',0.006129712152899999], + ['Ni60',0.0023611541470999996], + ['Ni61',0.0001026377359], + ['Ni62',0.0003272540145], + ['Ni64',8.334194959999999e-05], + ['Al27',0.00034646], + ['Ti46',2.419395e-05], + ['Ti47',2.1818543999999998e-05], + ['Ti48',0.000216191272], + ['Ti49',1.5865366e-05], + ['Ti50',1.5190867999999998e-05], + ['H1',2.271046252164e-05], + ['H2',3.53747836e-09], + ['Si28',0.0009221861243840001], + ['Si29',4.682598020800001e-05], + ['Si30',3.0867895408e-05], + ['V50',2.303175e-07], + ['V51',9.18966825e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-2.6272, bc='reflective') +s2 = mcdc.surface('plane-x', x=-2.551, bc='interface') +s3 = mcdc.surface('plane-x', x=-2.5335, bc='interface') +s4 = mcdc.surface('plane-x', x=2.5335, bc='interface') +s5 = mcdc.surface('plane-x', x=2.551, bc='interface') +s6 = mcdc.surface('plane-x', x=2.6272, bc='reflective') +s7 = mcdc.surface('plane-y', y=-2.6272, bc='reflective') +s8 = mcdc.surface('plane-y', y=-2.551, bc='interface') +s9 = mcdc.surface('plane-y', y=-2.5335, bc='interface') +s10 = mcdc.surface('plane-y', y=2.5335, bc='interface') +s11 = mcdc.surface('plane-y', y=2.551, bc='interface') +s12 = mcdc.surface('plane-y', y=2.6272, bc='reflective') +s13 = mcdc.surface('plane-z', z=-1.11125, bc='reflective') +s14 = mcdc.surface('plane-z', z=-0.79375, bc='interface') +s15 = mcdc.surface('plane-z', z=-0.47625, bc='interface') +s16 = mcdc.surface('plane-z', z=-0.15875, bc='interface') +s17 = mcdc.surface('plane-z', z=0.15875, bc='interface') +s18 = mcdc.surface('plane-z', z=0.47625, bc='interface') +s19 = mcdc.surface('plane-z', z=0.79375, bc='interface') +s20 = mcdc.surface('plane-z', z=1.11125, bc='reflective') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s13 & -s14, fill=m2) +c2 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s14 & -s15, fill=m2) +c3 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s15 & -s16, fill=m2) +c4 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s16 & -s17, fill=m1) +c5 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s17 & -s18, fill=m2) +c6 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s18 & -s19, fill=m2) +c7 = mcdc.cell(+s3 & -s4 & +s9 & -s10 & +s19 & -s20, fill=m2) +c8 = mcdc.cell(+s2 & -s3 & +s8 & -s11 & +s13 & -s20, fill=mvoid) +c9 = mcdc.cell(+s3 & -s4 & +s8 & -s9 & +s13 & -s20, fill=mvoid) +c10 = mcdc.cell(+s4 & -s5 & +s8 & -s11 & +s13 & -s20, fill=mvoid) +c11 = mcdc.cell(+s3 & -s4 & +s10 & -s11 & +s13 & -s20, fill=mvoid) +c12 = mcdc.cell(+s1 & -s2 & +s7 & -s12 & +s13 & -s20, fill=m3) +c13 = mcdc.cell(+s2 & -s5 & +s7 & -s8 & +s13 & -s20, fill=m3) +c14 = mcdc.cell(+s5 & -s6 & +s7 & -s12 & +s13 & -s20, fill=m3) +c15 = mcdc.cell(+s2 & -s5 & +s11 & -s12 & +s13 & -s20, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-2.6272,2.6272], y=[-2.6272,2.6272], z=[-1.11125,1.11125], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-fast-008/openmc/8h/generate_materials.py b/icsbep/openmc/mix-met-fast-008/openmc/8h/generate_materials.py new file mode 100644 index 0000000..e8dc2c5 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-008/openmc/8h/generate_materials.py @@ -0,0 +1,46 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Enriched U metal (37.5 w/o)" +mat.set_density('sum') +mat.add_nuclide('U235', 1.7730e-02) +mat.add_nuclide('U238', 2.8957e-02) +mat.add_element('C', 1.8452e-04) +mat.add_element('O', 3.4631e-04) +mat.add_element('Fe', 5.9527e-05) +mat.add_element('Al', 4.1070e-05) +mat.add_element('H', 4.3978e-05) +mat.add_element('Si', 3.9456e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Natural U metal" +mat.set_density('sum') +mat.add_nuclide('U235', 3.3316e-04) +mat.add_nuclide('U238', 4.5948e-02) +mat.add_element('C', 4.9205e-04) +mat.add_element('Fe', 1.0583e-04) +mat.add_element('H', 4.3978e-05) +mat.add_element('Si', 2.1043e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Sheath" +mat.set_density('sum') +mat.add_element('C', 7.7829e-04) +mat.add_element('Fe', 5.6624e-02) +mat.add_element('Cr', 1.6107e-02) +mat.add_element('Cu', 7.3853e-05) +mat.add_element('Mo', 1.4635e-04) +mat.add_element('Mn', 1.1918e-03) +mat.add_element('Ni', 9.0041e-03) +mat.add_element('Al', 3.4646e-04) +mat.add_element('Ti', 2.9326e-04) +mat.add_element('H', 2.2714e-05) +mat.add_element('Si', 9.9988e-04) +mat.add_element('V', 9.2127e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-fast-008/openmc/8h/geometry.xml b/icsbep/openmc/mix-met-fast-008/openmc/8h/geometry.xml new file mode 100644 index 0000000..c6531d6 --- /dev/null +++ b/icsbep/openmc/mix-met-fast-008/openmc/8h/geometry.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-008/openmc/8h/materials.xml b/icsbep/openmc/mix-met-fast-008/openmc/8h/materials.xml new file mode 100644 index 0000000..feb9c8d --- /dev/null +++ b/icsbep/openmc/mix-met-fast-008/openmc/8h/materials.xml @@ -0,0 +1,76 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-fast-008/openmc/8h/settings.xml b/icsbep/openmc/mix-met-fast-008/openmc/8h/settings.xml new file mode 100644 index 0000000..0f72b5d --- /dev/null +++ b/icsbep/openmc/mix-met-fast-008/openmc/8h/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -2.62720 -2.62720 -1.11125 + 2.62720 2.62720 1.11125 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/mix-met-inter-004/mcdc/mix-met-inter-004.py b/icsbep/openmc/mix-met-inter-004/mcdc/mix-met-inter-004.py new file mode 100644 index 0000000..9783127 --- /dev/null +++ b/icsbep/openmc/mix-met-inter-004/mcdc/mix-met-inter-004.py @@ -0,0 +1,183 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu240',0.000106605], + ['U235',6.02719e-06], + ['U238',0.00260196], + ['Pu239',0.0016549], + ['Pu242',3.42379e-07], + ['Am241',2.91589e-06], + ['Cr50',7.99805875e-05], + ['Cr52',0.0015423460175], + ['Cr53',0.0001748896575], + ['Cr54',4.35337375e-05], + ['Ni58',0.000538118621433], + ['Ni60',0.000207282329567], + ['Ni61',9.010419343e-06], + ['Ni62',2.8729159665000004e-05], + ['Ni64',7.316469992000001e-06], + ['Fe54',0.00042545228950000003], + ['Fe56',0.006678691081400001], + ['Fe57',0.0001542401029], + ['Fe58',2.0526526200000005e-05], + ['Al27',0.000110408], + ['C0',0.0556078], + ['Mo100',2.04131928e-05], + ['Mo92',3.0688922550000004e-05], + ['Mo94',1.9246305649999998e-05], + ['Mo95',3.3253141350000005e-05], + ['Mo96',3.492910135e-05], + ['Mo97',2.0073810900000003e-05], + ['Mo98',5.08905254e-05], + ['Mn55',9.83153e-05], + ['Cu63',1.930412145e-06], + ['Cu65',8.612178550000001e-07], + ['Si28',8.525361146415999e-05], + ['Si29',4.32893514392e-06], + ['Si30',2.8536533919199997e-06]]) +# Material Name: Axial blanket +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',8.28476e-05], + ['U238',0.039635], + ['Cr50',6.2969478e-05], + ['Cr52',0.0012143037036], + ['Cr53',0.00013769229240000001], + ['Cr54',3.4274526e-05], + ['Ni58',0.000421046776503], + ['Ni60',0.000162186464497], + ['Ni61',7.050133313e-06], + ['Ni62',2.2478910015e-05], + ['Ni64',5.7247156720000005e-06], + ['Fe54',0.0003405361295], + ['Fe56',0.0053456889694], + ['Fe57',0.00012345527089999999], + ['Fe58',1.6429630199999998e-05], + ['C0',1.3715100000000002e-05], + ['Mn55',7.06576e-05], + ['H1',3.97871e-06], + ['Si28',6.823686658544e-05], + ['Si29',3.46487339128e-06], + ['Si30',2.28406002328e-06], + ['Cl35',5.212406795309999e-06], + ['Cl37',1.66732320469e-06], + ['F19',2.03717e-05]]) +# Material Name: Radial blanket +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',8.34523e-05], + ['U238',0.0399253], + ['Cr50',4.8106102e-05], + ['Cr52',0.0009276782924000001], + ['Cr53',0.00010519127160000001], + ['Cr54',2.6184334000000006e-05], + ['Ni58',0.000308233822437], + ['Ni60',0.000118731116563], + ['Ni61',5.161159427e-06], + ['Ni62',1.6456034685000003e-05], + ['Ni64',4.190866888e-06], + ['Fe54',0.00026413613450000005], + ['Fe56',0.0041463724354000005], + ['Fe57',9.575782190000003e-05], + ['Fe58',1.2743608200000001e-05], + ['C0',8.4026e-06], + ['Mn55',4.35132e-05], + ['H1',2.43087e-06], + ['Si28',5.5884545543040005e-05], + ['Si29',2.83765777248e-06], + ['Si30',1.87059668448e-06], + ['Cl35',3.1933002697199996e-06], + ['Cl37',1.02145973028e-06], + ['F19',1.2481099999999998e-05]]) +# Material Name: Drawer gap +m4 = mcdc.material(nuclides=[ + ['Cr50',0.000150214471], + ['Cr52',0.0028967365501999997], + ['Cr53',0.0003284666718], + ['Cr54',8.1762307e-05], + ['Ni58',0.00108897170778], + ['Ni60',0.00041946995221999996], + ['Ni61',1.8234068379999998e-05], + ['Ni62',5.8138188900000003e-05], + ['Ni64',1.4806082720000002e-05], + ['Fe54',0.0011228946400000002], + ['Fe56',0.017627044448000003], + ['Fe57',0.000407085328], + ['Fe58',5.4175584000000006e-05], + ['C0',0.000262585], + ['Mn55',0.00023448700000000002], + ['Si28',0.0001391727425264], + ['Si29',7.066794776800001e-06], + ['Si30',4.6584626968e-06]]) +# Material Name: Matrix +m5 = mcdc.material(nuclides=[ + ['Cr50',4.821212000000001e-05], + ['Cr52',0.0009297227440000001], + ['Cr53',0.000105423096], + ['Cr54',2.6242040000000003e-05], + ['Ni58',0.000308765503026], + ['Ni60',0.00011893591897399999], + ['Ni61',5.170062046e-06], + ['Ni62',1.648442013e-05], + ['Ni64',4.198095824e-06], + ['Fe54',0.000264759796], + ['Fe56',0.0041561625872], + ['Fe57',9.59839192e-05], + ['Fe58',1.27736976e-05], + ['Mn55',4.34957e-05], + ['Si28',5.604797653600001e-05], + ['Si29',2.8459563320000004e-06], + ['Si30',1.8760671320000001e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=34.3564, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=68.4995, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=96.8226, bc='vacuum') +s4 = mcdc.surface('plane-z', z=0.0, bc='reflective') +s5 = mcdc.surface('plane-z', z=30.5631, bc='interface') +s6 = mcdc.surface('plane-z', z=53.4231, bc='interface') +s7 = mcdc.surface('plane-z', z=54.0581, bc='interface') +s8 = mcdc.surface('plane-z', z=60.96, bc='interface') +s9 = mcdc.surface('plane-z', z=61.6781, bc='interface') +s10 = mcdc.surface('plane-z', z=85.09, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & +s4 & -s5, fill=m1) +c2 = mcdc.cell(-s1 & +s5 & -s6, fill=m2) +c3 = mcdc.cell(-s1 & +s7 & -s9, fill=m2) +c4 = mcdc.cell(-s1 & +s6 & -s7, fill=m4) +c5 = mcdc.cell(+s1 & -s2 & +s4 & -s8, fill=m3) +c6 = mcdc.cell(-s1 & +s9 & -s10, fill=m5) +c7 = mcdc.cell(+s1 & -s2 & +s8 & -s10, fill=m5) +c8 = mcdc.cell(+s2 & -s3 & +s4 & -s10, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-97.0,97.0], y=[-97.0,97.0], z=[0.0,86.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/mix-met-inter-004/openmc/generate_materials.py b/icsbep/openmc/mix-met-inter-004/openmc/generate_materials.py new file mode 100644 index 0000000..d6695dc --- /dev/null +++ b/icsbep/openmc/mix-met-inter-004/openmc/generate_materials.py @@ -0,0 +1,79 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Core" +mat.set_density('sum') +mat.add_nuclide('Pu240', 1.06605E-04) +mat.add_nuclide('Pu241', 8.37189E-06) +mat.add_nuclide('U235', 6.02719E-06) +mat.add_nuclide('U238', 2.60196E-03) +mat.add_nuclide('Pu239', 1.65490E-03) +mat.add_nuclide('Pu242', 3.42379E-07) +mat.add_nuclide('Am241', 2.91589E-06) +mat.add_element('Cr', 1.84075E-03) +mat.add_element('Ni', 7.90457E-04) +mat.add_element('Fe', 7.27891E-03) +mat.add_element('Al', 1.10408E-04) +mat.add_element('C', 5.56078E-02) +mat.add_element('Mo', 2.09495E-04) +mat.add_nuclide('Mn55', 9.83153E-05) +mat.add_element('Cu', 2.79163E-06) +mat.add_element('Si', 9.24362E-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Axial blanket" +mat.set_density('sum') +mat.add_nuclide('U235', 8.28476E-05) +mat.add_nuclide('U238', 3.96350E-02) +mat.add_element('Cr', 1.44924E-03) +mat.add_element('Ni', 6.18487E-04) +mat.add_element('Fe', 5.82611E-03) +mat.add_element('C', 1.37151E-05) +mat.add_nuclide('Mn55', 7.06576E-05) +mat.add_nuclide('H1', 3.97871E-06) +mat.add_element('Si', 7.39858E-05) +mat.add_element('Cl', 6.87973E-06) +mat.add_nuclide('F19', 2.03717E-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Radial blanket" +mat.set_density('sum') +mat.add_nuclide('U235', 8.34523E-05) +mat.add_nuclide('U238', 3.99253E-02) +mat.add_element('Cr', 1.10716E-03) +mat.add_element('Ni', 4.52773E-04) +mat.add_element('Fe', 4.51901E-03) +mat.add_element('C', 8.40260E-06) +mat.add_nuclide('Mn55', 4.35132E-05) +mat.add_nuclide('H1', 2.43087E-06) +mat.add_element('Si', 6.05928E-05) +mat.add_element('Cl', 4.21476E-06) +mat.add_nuclide('F19', 1.24811E-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Drawer gap" +mat.set_density('sum') +mat.add_element('Cr', 3.45718E-03) +mat.add_element('Ni', 1.59962E-03) +mat.add_element('Fe', 1.92112E-02) +mat.add_element('C', 2.62585E-04) +mat.add_nuclide('Mn55', 2.34487E-04) +mat.add_element('Si', 1.50898E-04) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Matrix" +mat.set_density('sum') +mat.add_element('Cr', 1.10960E-03) +mat.add_element('Ni', 4.53554E-04) +mat.add_element('Fe', 4.52968E-03) +mat.add_nuclide('Mn55', 4.34957E-05) +mat.add_element('Si', 6.07700E-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/mix-met-inter-004/openmc/geometry.xml b/icsbep/openmc/mix-met-inter-004/openmc/geometry.xml new file mode 100644 index 0000000..7973f7c --- /dev/null +++ b/icsbep/openmc/mix-met-inter-004/openmc/geometry.xml @@ -0,0 +1,46 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-inter-004/openmc/materials.xml b/icsbep/openmc/mix-met-inter-004/openmc/materials.xml new file mode 100644 index 0000000..096eb2f --- /dev/null +++ b/icsbep/openmc/mix-met-inter-004/openmc/materials.xml @@ -0,0 +1,136 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/mix-met-inter-004/openmc/settings.xml b/icsbep/openmc/mix-met-inter-004/openmc/settings.xml new file mode 100644 index 0000000..9ce6e52 --- /dev/null +++ b/icsbep/openmc/mix-met-inter-004/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -97. -97. 0. 97. 97. 86. + + + + \ No newline at end of file diff --git a/icsbep/openmc/prepare_jobs.sh b/icsbep/openmc/prepare_jobs.sh new file mode 100755 index 0000000..8a8c8c7 --- /dev/null +++ b/icsbep/openmc/prepare_jobs.sh @@ -0,0 +1,44 @@ +#!/bin/bash + +# Set number of particles, inactive batches, and total batches +PARTICLES=50000 +INACTIVE=100 +BATCHES=5100 + +# Check for argument -- if one exists, we assume it is a file with the list of +# directories to run. Otherwise, we simply search for directories containing a +# settings.xml file +if [[ $# -gt 0 ]] +then + directories=$(cat $1) +else + directories=$(find . -name settings.xml | sed 's/\/settings.xml//g' | sort) +fi + +for dir in $directories +do + echo Preparing ${dir}... + + # If qsub exists, create a pbs file to execute a job + if [[ $(command -v qsub) ]] + then + cat < $dir/openmc.pbs +#!/bin/sh + +#PBS -l nodes=2:ppn=8 +#PBS -l walltime=48:00:00 +#PBS -j oe + +cd \$PBS_O_WORKDIR +PATH=\$PBS_O_PATH + +echo \$PBS_O_WORKDIR +mpiexec -rmk pbs openmc +EOF + fi + + # Change number of batches and particles + sed -i -e "s/\(\).*\(<\/particles>\)/\1${PARTICLES}\2/g" $dir/settings.xml + sed -i -e "s/\(\).*\(<\/inactive>\)/\1${INACTIVE}\2/g" $dir/settings.xml + sed -i -e "s/\(\).*\(<\/batches>\)/\1${BATCHES}\2/g" $dir/settings.xml +done diff --git a/icsbep/openmc/pu-comp-inter-001/mcdc/pu-comp-inter-001.py b/icsbep/openmc/pu-comp-inter-001/mcdc/pu-comp-inter-001.py new file mode 100644 index 0000000..759d1fa --- /dev/null +++ b/icsbep/openmc/pu-comp-inter-001/mcdc/pu-comp-inter-001.py @@ -0,0 +1,55 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# S(a,b): c_Graphite (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.0002735], + ['Pu240',1.549e-05], + ['Pu242',5.8e-08], + ['H1',0.0001077], + ['B10',0.00010151], + ['B11',0.00040859], + ['C0',0.0709], + ['O16',0.002705974047], + ['O17',1.025953e-06], + ['Ca40',0.00080267148], + ['Ca42',5.357160000000001e-06], + ['Ca43',1.1178e-06], + ['Ca44',1.727208e-05], + ['Ca46',3.312e-08], + ['Ca48',1.5483599999999998e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=100.0, bc='reflective') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-comp-inter-001/openmc/generate_materials.py b/icsbep/openmc/pu-comp-inter-001/openmc/generate_materials.py new file mode 100644 index 0000000..e9ccbec --- /dev/null +++ b/icsbep/openmc/pu-comp-inter-001/openmc/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.735e-04) +mat.add_nuclide('Pu240', 1.549e-05) +mat.add_nuclide('Pu241', 1.072e-06) +mat.add_nuclide('Pu242', 5.800e-08) +mat.add_nuclide('H1', 1.077e-04) +mat.add_nuclide('B10', 1.0151e-04) +mat.add_nuclide('B11', 4.0859e-04) +mat.add_element('C', 7.090e-02) +mat.add_element('O', 2.707e-03) +mat.add_element('Ca', 8.280e-04) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-comp-inter-001/openmc/geometry.xml b/icsbep/openmc/pu-comp-inter-001/openmc/geometry.xml new file mode 100644 index 0000000..1556010 --- /dev/null +++ b/icsbep/openmc/pu-comp-inter-001/openmc/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + diff --git a/icsbep/openmc/pu-comp-inter-001/openmc/materials.xml b/icsbep/openmc/pu-comp-inter-001/openmc/materials.xml new file mode 100644 index 0000000..2d79beb --- /dev/null +++ b/icsbep/openmc/pu-comp-inter-001/openmc/materials.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-comp-inter-001/openmc/settings.xml b/icsbep/openmc/pu-comp-inter-001/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-comp-inter-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-001/mcdc/pu-met-fast-001.py b/icsbep/openmc/pu-met-fast-001/mcdc/pu-met-fast-001.py new file mode 100644 index 0000000..103ee41 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-001/mcdc/pu-met-fast-001.py @@ -0,0 +1,43 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037047], + ['Pu240',0.0017512], + ['Ga69',0.0008266052159999999], + ['Ga71',0.000548594784]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.3849, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-001/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-001/openmc/generate_materials.py new file mode 100644 index 0000000..2e14977 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-001/openmc/generate_materials.py @@ -0,0 +1,13 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7047e-02) +mat.add_nuclide('Pu240', 1.7512e-03) +mat.add_nuclide('Pu241', 1.1674e-04) +mat.add_element('Ga', 1.3752e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-001/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-001/openmc/geometry.xml new file mode 100644 index 0000000..88ffbc4 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-001/openmc/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-001/openmc/materials.xml b/icsbep/openmc/pu-met-fast-001/openmc/materials.xml new file mode 100644 index 0000000..24f8cdb --- /dev/null +++ b/icsbep/openmc/pu-met-fast-001/openmc/materials.xml @@ -0,0 +1,11 @@ + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-001/openmc/settings.xml b/icsbep/openmc/pu-met-fast-001/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-002/mcdc/pu-met-fast-002.py b/icsbep/openmc/pu-met-fast-002/mcdc/pu-met-fast-002.py new file mode 100644 index 0000000..40b7c03 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-002/mcdc/pu-met-fast-002.py @@ -0,0 +1,21 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.029934], + ['Pu240',0.0078754], + ['Pu242',0.00015672], + ['Ga69',0.000824801976], + ['Ga71',0.0005473980240000001]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) diff --git a/icsbep/openmc/pu-met-fast-002/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-002/openmc/generate_materials.py new file mode 100644 index 0000000..8dfe997 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-002/openmc/generate_materials.py @@ -0,0 +1,14 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.9934e-02) +mat.add_nuclide('Pu240', 7.8754e-03) +mat.add_nuclide('Pu241', 1.2146e-03) +mat.add_nuclide('Pu242', 1.5672e-04) +mat.add_element('Ga', 1.3722e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-002/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-002/openmc/geometry.xml new file mode 100644 index 0000000..8f76c7b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-002/openmc/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + sphere + 0. 0. 0. 6.6595 + vacuum + + + diff --git a/icsbep/openmc/pu-met-fast-002/openmc/materials.xml b/icsbep/openmc/pu-met-fast-002/openmc/materials.xml new file mode 100644 index 0000000..7f5b70a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-002/openmc/materials.xml @@ -0,0 +1,12 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-002/openmc/settings.xml b/icsbep/openmc/pu-met-fast-002/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-002/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-003/mcdc/pu-met-fast-003_case-103.py b/icsbep/openmc/pu-met-fast-003/mcdc/pu-met-fast-003_case-103.py new file mode 100644 index 0000000..0b6166d --- /dev/null +++ b/icsbep/openmc/pu-met-fast-003/mcdc/pu-met-fast-003_case-103.py @@ -0,0 +1,136 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Pure Pu +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.04601], + ['Pu240',0.0029236], + ['Pu242',4.8566e-06]]) +# Material Name: Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.060263]]) +# Material Name: Aluminum +m3 = mcdc.material(nuclides=[ + ['Al27',0.053031]]) +# Material Name: Al Heat Sink: Top +m4 = mcdc.material(nuclides=[ + ['Al27',0.036742]]) +# Material Name: Al Heat Sink: Bottom +m5 = mcdc.material(nuclides=[ + ['Al27',0.030139]]) +# Material Name: Steel +m6 = mcdc.material(nuclides=[ + ['Fe54',0.004916930900000001], + ['Fe56',0.07718529988], + ['Fe57',0.0017825451800000001], + ['Fe58',0.00023722404000000002]]) +# Material Name: Steel (Table Support at 7% density) +m7 = mcdc.material(nuclides=[ + ['Fe54',0.000344182825], + ['Fe56',0.00540293429], + ['Fe57',0.000124777315], + ['Fe58',1.660557e-05]]) +# Material Name: Stainless Steel: Shoe +m8 = mcdc.material(nuclides=[ + ['Al27',0.02926], + ['Fe54',0.00045538979499999997], + ['Fe56',0.007148645893999999], + ['Fe57',0.000165093409], + ['Fe58',2.1970902e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-66.0, bc='vacuum') +s2 = mcdc.surface('plane-x', x=66.0, bc='vacuum') +s3 = mcdc.surface('plane-y', y=-23.0, bc='vacuum') +s4 = mcdc.surface('plane-y', y=23.0, bc='vacuum') +s5 = mcdc.surface('plane-z', z=-32.54, bc='vacuum') +s6 = mcdc.surface('plane-z', z=-2.54, bc='interface') +s7 = mcdc.surface('plane-z', z=0.0, bc='interface') +s8 = mcdc.surface('plane-z', z=8.3, bc='interface') +s9 = mcdc.surface('plane-z', z=14.529, bc='interface') +s10 = mcdc.surface('plane-z', z=15.164, bc='interface') +s11 = mcdc.surface('plane-z', z=15.185, bc='interface') +s12 = mcdc.surface('plane-z', z=19.818, bc='interface') +s13 = mcdc.surface('plane-z', z=19.905, bc='interface') +s14 = mcdc.surface('plane-z', z=20.384, bc='interface') +s15 = mcdc.surface('plane-z', z=22.239, bc='interface') +s16 = mcdc.surface('plane-z', z=22.874, bc='interface') +s17 = mcdc.surface('plane-z', z=22.895, bc='interface') +s18 = mcdc.surface('plane-z', z=27.528, bc='interface') +s19 = mcdc.surface('plane-z', z=27.615, bc='interface') +s20 = mcdc.surface('plane-z', z=28.094, bc='interface') +s21 = mcdc.surface('plane-z', z=29.949, bc='interface') +s22 = mcdc.surface('plane-z', z=30.584, bc='interface') +s23 = mcdc.surface('plane-z', z=30.605, bc='interface') +s24 = mcdc.surface('plane-z', z=35.238, bc='interface') +s25 = mcdc.surface('plane-z', z=35.325, bc='interface') +s26 = mcdc.surface('plane-z', z=35.804, bc='interface') +s27 = mcdc.surface('plane-z', z=45.733, bc='vacuum') +s28 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.104, bc='interface') +s29 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.326, bc='interface') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.2625, bc='interface') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.2995, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.425, bc='interface') +s33 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=3.609, bc='interface') +s40 = mcdc.surface('plane-x', x=-14.4, bc='interface') +s41 = mcdc.surface('plane-x', x=14.4, bc='interface') +s42 = mcdc.surface('plane-y', y=-14.4, bc='interface') +s43 = mcdc.surface('plane-y', y=14.4, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & +s3 & -s4 & +s5 & -s6, fill=m7) +c2 = mcdc.cell(+s1 & -s2 & +s3 & -s4 & +s6 & -s7, fill=m3) +c3 = mcdc.cell(-s8 & -s32, fill=m8) +c4 = mcdc.cell(+s8 & -s9 & -s28, fill=mvoid) +c5 = mcdc.cell(+s8 & -s9 & +s28 & -s29, fill=m2) +c6 = mcdc.cell(+s8 & -s9 & +s29 & -s32, fill=mvoid) +c7 = mcdc.cell(+s26 & -s32, fill=mvoid) +c8 = mcdc.cell(+s32 & -s33, fill=m2) +c80 = mcdc.cell(+s33, fill=mvoid) +c9 = mcdc.cell(+s9 & -s10 & -s31, fill=m5) +c10 = mcdc.cell(+s10 & -s11 & -s31, fill=m6) +c11 = mcdc.cell(+s11 & -s12 & -s30, fill=m1) +c12 = mcdc.cell(+s11 & -s12 & +s30 & -s31, fill=m2) +c13 = mcdc.cell(+s12 & -s13 & -s31, fill=m2) +c14 = mcdc.cell(+s13 & -s14 & -s31, fill=m4) +c15 = mcdc.cell(+s9 & -s14 & +s31 & -s32, fill=mvoid) +c16 = mcdc.cell(+s14 & -s15 & -s28, fill=mvoid) +c17 = mcdc.cell(+s14 & -s15 & +s28 & -s29, fill=m2) +c18 = mcdc.cell(+s14 & -s15 & +s29 & -s32, fill=mvoid) +c19 = mcdc.cell(+s15 & -s16 & -s31, fill=m5) +c20 = mcdc.cell(+s16 & -s17 & -s31, fill=m6) +c21 = mcdc.cell(+s17 & -s18 & -s30, fill=m1) +c22 = mcdc.cell(+s17 & -s18 & +s30 & -s31, fill=m2) +c23 = mcdc.cell(+s18 & -s19 & -s31, fill=m2) +c24 = mcdc.cell(+s19 & -s20 & -s31, fill=m4) +c25 = mcdc.cell(+s15 & -s20 & +s31 & -s32, fill=mvoid) +c26 = mcdc.cell(+s20 & -s21 & -s28, fill=mvoid) +c27 = mcdc.cell(+s20 & -s21 & +s28 & -s29, fill=m2) +c28 = mcdc.cell(+s20 & -s21 & +s29 & -s32, fill=mvoid) +c29 = mcdc.cell(+s21 & -s22 & -s31, fill=m5) +c30 = mcdc.cell(+s22 & -s23 & -s31, fill=m6) +c31 = mcdc.cell(+s23 & -s24 & -s30, fill=m1) +c32 = mcdc.cell(+s23 & -s24 & +s30 & -s31, fill=m2) +c33 = mcdc.cell(+s24 & -s25 & -s31, fill=m2) +c34 = mcdc.cell(+s25 & -s26 & -s31, fill=m4) +c35 = mcdc.cell(+s21 & -s26 & +s31 & -s32, fill=mvoid) +c37 = mcdc.cell(+s1 & -s2 & +s3 & -s42 & +s7 & -s27, fill=mvoid) +c38 = mcdc.cell(+s1 & -s40 & +s42 & -s43 & +s7 & -s27, fill=mvoid) +c39 = mcdc.cell(+s41 & -s2 & +s42 & -s43 & +s7 & -s27, fill=mvoid) +c40 = mcdc.cell(+s1 & -s2 & +s43 & -s4 & +s7 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 100 +Lattice100 = mcdc.lattice(x=[-14.4, 9.6, 3], y=[-14.4, 9.6, 3], \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-003/openmc/case-103/generate_materials.py b/icsbep/openmc/pu-met-fast-003/openmc/case-103/generate_materials.py new file mode 100644 index 0000000..dac7e2a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-003/openmc/case-103/generate_materials.py @@ -0,0 +1,57 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Pure Pu" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.6010e-02) +mat.add_nuclide('Pu240', 2.9236e-03) +mat.add_nuclide('Pu241', 2.2433e-04) +mat.add_nuclide('Pu242', 4.8566e-06) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_element('Al', 6.0263e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.3031e-02) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Al Heat Sink: Top" +mat.set_density('sum') +mat.add_element('Al', 3.6742e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Al Heat Sink: Bottom" +mat.set_density('sum') +mat.add_element('Al', 3.0139e-02) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel" +mat.set_density('sum') +mat.add_element('Fe', 8.4122e-02) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Steel (Table Support at 7% density)" +mat.set_density('sum') +mat.add_element('Fe', 5.8885e-03) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Stainless Steel: Shoe" +mat.set_density('sum') +mat.add_element('Al', 2.9260e-02) +mat.add_element('Fe', 7.7911e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-003/openmc/case-103/geometry.xml b/icsbep/openmc/pu-met-fast-003/openmc/case-103/geometry.xml new file mode 100644 index 0000000..2843462 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-003/openmc/case-103/geometry.xml @@ -0,0 +1,120 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 3 3 + -14.4 -14.4 + 9.60 9.60 + + 1 1 1 + 1 1 1 + 1 1 1 + + + + diff --git a/icsbep/openmc/pu-met-fast-003/openmc/case-103/materials.xml b/icsbep/openmc/pu-met-fast-003/openmc/case-103/materials.xml new file mode 100644 index 0000000..794f193 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-003/openmc/case-103/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-003/openmc/case-103/plots.xml b/icsbep/openmc/pu-met-fast-003/openmc/case-103/plots.xml new file mode 100644 index 0000000..3840817 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-003/openmc/case-103/plots.xml @@ -0,0 +1,32 @@ + + + + + + + xz + 0. 0. 0. + 100. 100. + 1000 1000 + + + + xy + 0. 0. 16. + 32. 32. + 1000 1000 + + + + xy + 0. 0. 16. + 9.6 9.6 + 1000 1000 + + + diff --git a/icsbep/openmc/pu-met-fast-003/openmc/case-103/settings.xml b/icsbep/openmc/pu-met-fast-003/openmc/case-103/settings.xml new file mode 100644 index 0000000..e28c338 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-003/openmc/case-103/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + fission + -14.4 -14.4 15.185 14.4 14.4 35.238 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-005/mcdc/pu-met-fast-005.py b/icsbep/openmc/pu-met-fast-005/mcdc/pu-met-fast-005.py new file mode 100644 index 0000000..081dea3 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-005/mcdc/pu-met-fast-005.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037291], + ['Pu240',0.0019277], + ['Ga69',0.0008191518239999999], + ['Ga71',0.0005436481759999999]]) +m2 = mcdc.material(nuclides=[ + ['W180',6.17616e-05], + ['W182',0.01363902], + ['W183',0.0073650708], + ['W184',0.0157697952], + ['W186',0.0146323524], + ['Ni58',0.006611900835599999], + ['Ni60',0.0025468923643999996], + ['Ni61',0.00011071164759999998], + ['Ni62',0.000352997178], + ['Ni64',8.98979744e-05], + ['Cu63',0.0028195221], + ['Cu65',0.0012578779000000002], + ['Zr90',0.00040917155999999993], + ['Zr91',8.923041599999999e-05], + ['Zr92',0.00013639052], + ['Zr94',0.000138219664], + ['Zr96',2.226784e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0419, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.7409, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-005/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-005/openmc/generate_materials.py new file mode 100644 index 0000000..1fd61ec --- /dev/null +++ b/icsbep/openmc/pu-met-fast-005/openmc/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7291e-02) +mat.add_nuclide('Pu240', 1.9277e-03) +mat.add_nuclide('Pu241', 1.2196e-04) +mat.add_element('Ga', 1.3628e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.set_density('sum') +mat.add_element('W', 5.1468e-02) +mat.add_element('Ni', 9.7124e-03) +mat.add_element('Cu', 4.0774e-03) +mat.add_element('Zr', 7.9528e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-005/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-005/openmc/geometry.xml new file mode 100644 index 0000000..9d784ab --- /dev/null +++ b/icsbep/openmc/pu-met-fast-005/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-005/openmc/materials.xml b/icsbep/openmc/pu-met-fast-005/openmc/materials.xml new file mode 100644 index 0000000..6fe7745 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-005/openmc/materials.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-005/openmc/settings.xml b/icsbep/openmc/pu-met-fast-005/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-005/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-006/mcdc/pu-met-fast-006.py b/icsbep/openmc/pu-met-fast-006/mcdc/pu-met-fast-006.py new file mode 100644 index 0000000..7346e71 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-006/mcdc/pu-met-fast-006.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036697], + ['Pu240',0.00187], + ['Ga69',0.0008868935399999999], + ['Ga71',0.00058860646]]) +# Material Name: Reflector +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.0003461], + ['U238',0.047721]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.5332, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=24.142, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-006/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-006/openmc/generate_materials.py new file mode 100644 index 0000000..31d5d32 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-006/openmc/generate_materials.py @@ -0,0 +1,15 @@ +import openmc + +core = openmc.Material(name='Core') +core.add_nuclide('Pu239', 3.6697e-02) +core.add_nuclide('Pu240', 1.8700e-03) +core.add_nuclide('Pu241', 1.1639e-04) +core.add_element('Ga', 1.4755e-03) + +reflector = openmc.Material(name='Reflector') +reflector.add_nuclide('U234', 2.6438e-06) +reflector.add_nuclide('U235', 3.4610e-04) +reflector.add_nuclide('U238', 4.7721e-02) + +materials = openmc.Materials([core, reflector]) +materials.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-006/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-006/openmc/geometry.xml new file mode 100644 index 0000000..4642a73 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-006/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-006/openmc/materials.xml b/icsbep/openmc/pu-met-fast-006/openmc/materials.xml new file mode 100644 index 0000000..bbd19e5 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-006/openmc/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-006/openmc/settings.xml b/icsbep/openmc/pu-met-fast-006/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-006/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-008/mcdc/pu-met-fast-008_case-1.py b/icsbep/openmc/pu-met-fast-008/mcdc/pu-met-fast-008_case-1.py new file mode 100644 index 0000000..d3b0813 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/mcdc/pu-met-fast-008_case-1.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036049], + ['Pu240',0.0019562], + ['Ga69',0.000801720504], + ['Ga71',0.000532079496]]) +# Material Name: Thorium reflector +# Depletable +m2 = mcdc.material(nuclides=[ +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.31, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=29.88, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-008/mcdc/pu-met-fast-008_case-2.py b/icsbep/openmc/pu-met-fast-008/mcdc/pu-met-fast-008_case-2.py new file mode 100644 index 0000000..596226f --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/mcdc/pu-met-fast-008_case-2.py @@ -0,0 +1,51 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036049], + ['Pu240',0.0019562], + ['Ga69',0.000801720504], + ['Ga71',0.000532079496]]) +# Material Name: Thorium reflector +# Depletable +m2 = mcdc.material(nuclides=[ +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.31, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=26.67, bc='vacuum') +s3 = mcdc.surface('plane-z', z=-26.67, bc='vacuum') +s4 = mcdc.surface('plane-z', z=26.67, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2 & +s3 & -s4, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-008/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..ce5189d --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-1/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6049e-02) +mat.add_nuclide('Pu240', 1.9562e-03) +mat.add_nuclide('Pu241', 1.1459e-04) +mat.add_element('Ga', 1.3338e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Thorium reflector" +mat.set_density('sum') +mat.add_nuclide('Th232', 3.0054e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-008/openmc/case-1/geometry.xml new file mode 100644 index 0000000..14c233b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-1/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-008/openmc/case-1/materials.xml new file mode 100644 index 0000000..231f451 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-1/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-008/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-008/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..ce5189d --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-2/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium core" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6049e-02) +mat.add_nuclide('Pu240', 1.9562e-03) +mat.add_nuclide('Pu241', 1.1459e-04) +mat.add_element('Ga', 1.3338e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Thorium reflector" +mat.set_density('sum') +mat.add_nuclide('Th232', 3.0054e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-008/openmc/case-2/geometry.xml new file mode 100644 index 0000000..14d119e --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-008/openmc/case-2/materials.xml new file mode 100644 index 0000000..231f451 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-2/materials.xml @@ -0,0 +1,15 @@ + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-008/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-008/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-008/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-009/mcdc/pu-met-fast-009.py b/icsbep/openmc/pu-met-fast-009/mcdc/pu-met-fast-009.py new file mode 100644 index 0000000..e4f8a69 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-009/mcdc/pu-met-fast-009.py @@ -0,0 +1,58 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Core +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037592], + ['Pu240',0.0019349], + ['Ga69',0.0008254631639999998], + ['Ga71',0.000547836836]]) +# Material Name: Reflector +m2 = mcdc.material(nuclides=[ + ['Al27',0.058787], + ['Cu63',0.0008131348499999999], + ['Cu65',0.00036276514999999997], + ['Si28',0.000223075927016], + ['Si29',1.1327159091999999e-05], + ['Si30',7.466913892e-06], + ['Mn55',0.00024729], + ['Mg24',0.0002758232136], + ['Mg25',3.5005872e-05], + ['Mg26',3.85309144e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.5118, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.4366, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-009/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-009/openmc/generate_materials.py new file mode 100644 index 0000000..a1b73aa --- /dev/null +++ b/icsbep/openmc/pu-met-fast-009/openmc/generate_materials.py @@ -0,0 +1,17 @@ +import openmc + +core = openmc.Material(name='Core') +core.add_nuclide('Pu239', 3.7592e-02) +core.add_nuclide('Pu240', 1.9349e-03) +core.add_nuclide('Pu241', 1.1797e-04) +core.add_element('Ga', 1.3733e-03) + +reflector = openmc.Material(name='Reflector') +reflector.add_element('Al', 5.8787e-02) +reflector.add_element('Cu', 1.1759e-03) +reflector.add_element('Si', 2.4187e-04) +reflector.add_element('Mn', 2.4729e-04) +reflector.add_element('Mg', 3.4936e-04) + +materials = openmc.Materials([core, reflector]) +materials.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-009/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-009/openmc/geometry.xml new file mode 100644 index 0000000..2764140 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-009/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-009/openmc/materials.xml b/icsbep/openmc/pu-met-fast-009/openmc/materials.xml new file mode 100644 index 0000000..8d19a1e --- /dev/null +++ b/icsbep/openmc/pu-met-fast-009/openmc/materials.xml @@ -0,0 +1,24 @@ + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-009/openmc/settings.xml b/icsbep/openmc/pu-met-fast-009/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-009/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-010/mcdc/pu-met-fast-010.py b/icsbep/openmc/pu-met-fast-010/mcdc/pu-met-fast-010.py new file mode 100644 index 0000000..988e1ba --- /dev/null +++ b/icsbep/openmc/pu-met-fast-010/mcdc/pu-met-fast-010.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037291], + ['Pu240',0.0019277], + ['Ga69',0.0008191518239999999], + ['Ga71',0.0005436481759999999]]) +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00034902], + ['U238',0.047518]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0419, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.1694, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-010/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-010/openmc/generate_materials.py new file mode 100644 index 0000000..3ccfc7e --- /dev/null +++ b/icsbep/openmc/pu-met-fast-010/openmc/generate_materials.py @@ -0,0 +1,19 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7291e-02) +mat.add_nuclide('Pu240', 1.9277e-03) +mat.add_nuclide('Pu241', 1.2196e-04) +mat.add_element('Ga', 1.3628e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.set_density('sum') +mat.add_nuclide('U235', 3.4902e-04) +mat.add_nuclide('U238', 4.7518e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-010/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-010/openmc/geometry.xml new file mode 100644 index 0000000..b9056ae --- /dev/null +++ b/icsbep/openmc/pu-met-fast-010/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-010/openmc/materials.xml b/icsbep/openmc/pu-met-fast-010/openmc/materials.xml new file mode 100644 index 0000000..df6c459 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-010/openmc/materials.xml @@ -0,0 +1,16 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-010/openmc/settings.xml b/icsbep/openmc/pu-met-fast-010/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-010/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-011/mcdc/pu-met-fast-011.py b/icsbep/openmc/pu-met-fast-011/mcdc/pu-met-fast-011.py new file mode 100644 index 0000000..38c6168 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-011/mcdc/pu-met-fast-011.py @@ -0,0 +1,49 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.046982], + ['Pu240',0.0025852], + ['Pu242',9.9432e-06]]) +# S(a,b): c_H_in_H2O (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['H1',0.066766], + ['O16',0.033370347843000005], + ['O17',1.2652157000000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.1217, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=29.5217, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-011/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-011/openmc/generate_materials.py new file mode 100644 index 0000000..529a0ca --- /dev/null +++ b/icsbep/openmc/pu-met-fast-011/openmc/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.6982e-02) +mat.add_nuclide('Pu240', 2.5852e-03) +mat.add_nuclide('Pu241', 1.4915e-04) +mat.add_nuclide('Pu242', 9.9432e-06) +mats.append(mat) + +mat = openmc.Material(2) +mat.set_density('sum') +mat.add_nuclide('H1', 6.6766e-02) +mat.add_element('O', 3.3383e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-011/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-011/openmc/geometry.xml new file mode 100644 index 0000000..0cb4ed3 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-011/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-011/openmc/materials.xml b/icsbep/openmc/pu-met-fast-011/openmc/materials.xml new file mode 100644 index 0000000..1d45965 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-011/openmc/materials.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-011/openmc/settings.xml b/icsbep/openmc/pu-met-fast-011/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-011/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-018/mcdc/pu-met-fast-018.py b/icsbep/openmc/pu-met-fast-018/mcdc/pu-met-fast-018.py new file mode 100644 index 0000000..c90b365 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-018/mcdc/pu-met-fast-018.py @@ -0,0 +1,50 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037291], + ['Pu240',0.0019277], + ['Ga69',0.0008191518239999999], + ['Ga71',0.0005436481759999999]]) +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.11984], + ['O16',0.0013770778896], + ['O17',5.221104000000001e-07]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0419, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.73, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-018/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-018/openmc/generate_materials.py new file mode 100644 index 0000000..175019f --- /dev/null +++ b/icsbep/openmc/pu-met-fast-018/openmc/generate_materials.py @@ -0,0 +1,20 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7291e-02) +mat.add_nuclide('Pu240', 1.9277e-03) +mat.add_nuclide('Pu241', 1.2196e-04) +mat.add_element('Ga', 1.3628e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.set_density('sum') +mat.add_element('Be', 1.1984e-01) +mat.add_element('O', 1.3776e-03) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-018/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-018/openmc/geometry.xml new file mode 100644 index 0000000..a94ca27 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-018/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-018/openmc/materials.xml b/icsbep/openmc/pu-met-fast-018/openmc/materials.xml new file mode 100644 index 0000000..bd111ba --- /dev/null +++ b/icsbep/openmc/pu-met-fast-018/openmc/materials.xml @@ -0,0 +1,18 @@ + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-018/openmc/settings.xml b/icsbep/openmc/pu-met-fast-018/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-018/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-019/mcdc/pu-met-fast-019.py b/icsbep/openmc/pu-met-fast-019/mcdc/pu-met-fast-019.py new file mode 100644 index 0000000..d250a30 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-019/mcdc/pu-met-fast-019.py @@ -0,0 +1,110 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.03393], + ['Pu240',0.0035043], + ['Ga69',0.0013286873399999998], + ['Ga71',0.0008818126599999998], + ['C0',0.0030246], + ['Fe54',1.9010862500000002e-05], + ['Fe56',0.000298429885], + ['Fe57',6.8920475e-06], + ['Fe58',9.172050000000001e-07], + ['W180',8.891999999999999e-08], + ['W182',1.96365e-05], + ['W183',1.060371e-05], + ['W184',2.270424e-05], + ['W186',2.1066629999999998e-05], + ['Ni58',0.0009658069803], + ['Ni60',0.00037202711969999995], + ['Ni61',1.6171761299999998e-05], + ['Ni62',5.1562651500000004e-05], + ['Ni64',1.31314872e-05]]) +# Material Name: Reflector +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.12081], + ['O16',8.2032897744e-05], + ['O17',3.1102256000000005e-08], + ['C0',0.0001002], + ['Fe54',2.97738455e-06], + ['Fe56',4.6738570060000004e-05], + ['Fe57',1.0793974100000001e-06], + ['Fe58',1.4364798e-07]]) +# Material Name: Steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +# Material Name: Copper +m4 = mcdc.material(nuclides=[ + ['Cu63',0.0569553975], + ['Cu65',0.025409602499999996]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 1.05], radius=5.35, bc='interface') +s5 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=5.5, bc='interface') +s6 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.1, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 1.05], radius=11.0, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.15, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=1.0, bc='interface') +s12 = mcdc.surface('plane-z', z=1.2, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.7, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=14.0, bc='vacuum') +s16 = mcdc.surface('plane-z', z=-0.15, bc='interface') +s17 = mcdc.surface('plane-z', z=-14.15, bc='vacuum') +s18 = mcdc.surface('plane-z', z=14.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s3, fill=m1) +c3 = mcdc.cell(+s3 & -s4 & +s12, fill=mvoid) +c4 = mcdc.cell(+s3 & -s5 & +s11 & -s12, fill=mvoid) +c5 = mcdc.cell(+s3 & -s7 & -s16, fill=m2) +c6 = mcdc.cell(+s4 & +s6 & -s8 & +s12, fill=m2) +c7 = mcdc.cell(+s3 & +s10 & -s11 & -s15, fill=mvoid) +c8 = mcdc.cell(+s5 & +s11 & -s12 & -s15, fill=m3) +c9 = mcdc.cell(+s7 & -s10 & +s13 & -s15 & +s17, fill=mvoid) +c10 = mcdc.cell(+s8 & +s12 & -s15 & -s18, fill=mvoid) +c11 = mcdc.cell(+s7 & -s9 & -s13 & -s10, fill=m4) +c12 = mcdc.cell(+s9 & -s10 & -s14 & +s17, fill=m3) +c13 = mcdc.cell(+s9 & -s10 & -s13 & +s14 & +s17, fill=mvoid) +c14 = mcdc.cell(+s3 & -s7 & -s10 & +s16, fill=mvoid) +c15 = mcdc.cell(+s4 & -s6 & -s8 & +s12, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-0.6,0.6], y=[-0.6,0.6], z=[5.17,6.17], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-019/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-019/openmc/generate_materials.py new file mode 100644 index 0000000..469dd9f --- /dev/null +++ b/icsbep/openmc/pu-met-fast-019/openmc/generate_materials.py @@ -0,0 +1,27 @@ +import openmc + +pu = openmc.Material(name="Plutonium") +pu.add_nuclide('Pu239', 3.3930e-02) +pu.add_nuclide('Pu240', 3.5043e-03) +pu.add_nuclide('Pu241', 3.9189e-04) +pu.add_element('Ga', 2.2105e-03) +pu.add_element('C', 3.0246e-03) +pu.add_element('Fe', 3.2525e-04) +pu.add_element('W', 7.4100e-05) +pu.add_element('Ni', 1.4187e-03) + +reflector = openmc.Material(name="Reflector") +reflector.add_element('Be', 1.2081e-01) +reflector.add_element('O', 8.2064e-05) +reflector.add_element('C', 1.0020e-04) +reflector.add_element('Fe', 5.0939e-05) +reflector.add_s_alpha_beta('c_Be') + +steel = openmc.Material(name="Steel") +steel.add_element('Fe', 8.1174e-02) + +cu = openmc.Material(name="Copper") +cu.add_element('Cu', 8.2365e-02) + +materials = openmc.Materials([pu, reflector, steel, cu]) +materials.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-019/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-019/openmc/geometry.xml new file mode 100644 index 0000000..fecaed4 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-019/openmc/geometry.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-019/openmc/materials.xml b/icsbep/openmc/pu-met-fast-019/openmc/materials.xml new file mode 100644 index 0000000..c336940 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-019/openmc/materials.xml @@ -0,0 +1,50 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-019/openmc/plots.xml b/icsbep/openmc/pu-met-fast-019/openmc/plots.xml new file mode 100644 index 0000000..662333b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-019/openmc/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 0. + 35. 35. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-019/openmc/settings.xml b/icsbep/openmc/pu-met-fast-019/openmc/settings.xml new file mode 100644 index 0000000..cf74331 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-019/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -.6 -.6 5.17 .6 .6 6.17 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-020/mcdc/pu-met-fast-020.py b/icsbep/openmc/pu-met-fast-020/mcdc/pu-met-fast-020.py new file mode 100644 index 0000000..89d0378 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-020/mcdc/pu-met-fast-020.py @@ -0,0 +1,106 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium alloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.03393], + ['Pu240',0.0035043], + ['Ga69',0.0013286873399999998], + ['Ga71',0.0008818126599999999], + ['C0',0.00030246], + ['Fe54',1.9010862500000002e-05], + ['Fe56',0.000298429885], + ['Fe57',6.8920475e-06], + ['Fe58',9.17205e-07], + ['W180',8.892e-08], + ['W182',1.96365e-05], + ['W183',1.060371e-05], + ['W184',2.270424e-05], + ['W186',2.1066629999999995e-05], + ['Ni58',0.0009658069802999997], + ['Ni60',0.00037202711970000006], + ['Ni61',1.6171761299999998e-05], + ['Ni62',5.1562651500000004e-05], + ['Ni64',1.3131487200000002e-05]]) +# Material Name: Depleted Uranium +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.00023787], + ['U238',0.046738]]) +# Material Name: Duralumin +m3 = mcdc.material(nuclides=[ + ['Al27',0.058077], + ['Mg24',0.000815721732], + ['Mg25',0.00010352663999999999], + ['Mg26',0.00011395162799999999], + ['Mn55',0.00018284], + ['Cu63',0.0007834003500000001], + ['Cu65',0.00034949965000000003]]) +# Material Name: Fe +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0047446203], + ['Fe56',0.07448039196], + ['Fe57',0.00172007706], + ['Fe58',0.00022891068]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.61], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.61], radius=5.35, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.61], radius=9.15, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.61], radius=13.0, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=13.2, bc='interface') +s10 = mcdc.surface('plane-z', z=0.0, bc='interface') +s11 = mcdc.surface('plane-z', z=0.41, bc='interface') +s12 = mcdc.surface('plane-z', z=0.61, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=11.0, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.5, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=15.0, bc='vacuum') +s16 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.5, bc='interface') +s17 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=1.75, bc='interface') +s18 = mcdc.surface('plane-z', z=-16.2, bc='vacuum') +s19 = mcdc.surface('plane-z', z=14.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s3 & -s10, fill=m1) +c2 = mcdc.cell(+s2 & -s4 & +s12, fill=m1) +c3 = mcdc.cell(+s3 & -s5 & -s10 & +s17, fill=m2) +c4 = mcdc.cell(+s4 & -s6 & +s12 & +s17, fill=m2) +c5 = mcdc.cell(+s5 & -s7 & -s10, fill=m2) +c6 = mcdc.cell(+s6 & -s8 & +s12 & +s16, fill=m2) +c7 = mcdc.cell(+s7 & -s9 & -s13 & -s10, fill=m3) +c8 = mcdc.cell(+s9 & +s18 & -s14 & -s10, fill=m3) +c9 = mcdc.cell(+s11 & -s12 & -s15, fill=m4) +c10 = mcdc.cell(-s1 & -s10, fill=mvoid) +c11 = mcdc.cell(-s2 & +s12, fill=mvoid) +c12 = mcdc.cell(+s10 & -s11 & -s15, fill=mvoid) +c13 = mcdc.cell(+s7 & -s15 & -s10 & +s13 & +s18, fill=mvoid) +c14 = mcdc.cell(+s8 & -s15 & +s12 & -s19, fill=mvoid) +c15 = mcdc.cell(+s9 & +s18 & +s14 & -s13 & -s10, fill=mvoid) +c16 = mcdc.cell(+s3 & -s5 & -s17 & -s10, fill=mvoid) +c17 = mcdc.cell(+s4 & -s6 & -s17 & +s12, fill=mvoid) +c18 = mcdc.cell(+s6 & -s8 & +s12 & -s16, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# eigenvalue = + +# Simulation Parameters diff --git a/icsbep/openmc/pu-met-fast-020/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-020/openmc/generate_materials.py new file mode 100644 index 0000000..6b779fa --- /dev/null +++ b/icsbep/openmc/pu-met-fast-020/openmc/generate_materials.py @@ -0,0 +1,40 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium alloy" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.3930e-02) +mat.add_nuclide('Pu240', 3.5043e-03) +mat.add_nuclide('Pu241', 3.9189e-04) +mat.add_element('Ga', 2.2105e-03) +mat.add_element('C', 3.0246e-04) +mat.add_element('Fe', 3.2525e-04) +mat.add_element('W', 7.4100e-05) +mat.add_element('Ni', 1.4187e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Depleted Uranium" +mat.set_density('sum') +mat.add_nuclide('U235', 2.3787e-04) +mat.add_nuclide('U238', 4.6738e-02) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Duralumin" +mat.set_density('sum') +mat.add_element('Al', 5.8077e-02) +mat.add_element('Mg', 1.0332e-03) +mat.add_element('Mn', 1.8284e-04) +mat.add_element('Cu', 1.1329e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Fe" +mat.set_density('sum') +mat.add_element('Fe', 8.1174e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-020/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-020/openmc/geometry.xml new file mode 100644 index 0000000..4d2e879 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-020/openmc/geometry.xml @@ -0,0 +1,53 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-020/openmc/materials.xml b/icsbep/openmc/pu-met-fast-020/openmc/materials.xml new file mode 100644 index 0000000..a8dd6db --- /dev/null +++ b/icsbep/openmc/pu-met-fast-020/openmc/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-020/openmc/plots.xml b/icsbep/openmc/pu-met-fast-020/openmc/plots.xml new file mode 100644 index 0000000..662333b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-020/openmc/plots.xml @@ -0,0 +1,11 @@ + + + + + xz + 0. 0. 0. + 35. 35. + 1000 1000 + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-020/openmc/settings.xml b/icsbep/openmc/pu-met-fast-020/openmc/settings.xml new file mode 100644 index 0000000..23e5733 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-020/openmc/settings.xml @@ -0,0 +1,20 @@ + + + + + + + 3000 + 20 + 10000 + + + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-021/mcdc/pu-met-fast-021_case-1.py b/icsbep/openmc/pu-met-fast-021/mcdc/pu-met-fast-021_case-1.py new file mode 100644 index 0000000..d078f80 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/mcdc/pu-met-fast-021_case-1.py @@ -0,0 +1,169 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.044422], + ['Pu240',0.0021326], + ['C0',0.00019515], + ['Fe54',4.7895683500000004e-06], + ['Fe56',7.518598022e-05], + ['Fe57',1.7363721699999999e-06], + ['Fe58',2.3107926000000002e-07]]) +# Material Name: Berylium Reflector +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.12099], + ['O16',0.0010445039829000001], + ['O17',3.9601710000000004e-07]]) +# Material Name: Steel Cover +m3 = mcdc.material(nuclides=[ + ['Fe54',0.002997316], + ['Fe56',0.047051451200000004], + ['Fe57',0.0010866232], + ['Fe58',0.0001446096], + ['C0',0.00034757000000000006], + ['Si28',0.0008225504010800002], + ['Si29',4.1766762459999996e-05], + ['Si30',2.7532836460000002e-05], + ['Ti46',5.0353049999999994e-05], + ['Ti47',4.5409295999999995e-05], + ['Ti48',0.00044994264799999995], + ['Ti49',3.3019394e-05], + ['Ti50',3.1615612e-05], + ['Cr50',0.0006279394], + ['Cr52',0.01210918628], + ['Cr53',0.00137308452], + ['Cr54',0.0003417898], + ['Mn55',0.0015198000000000002], + ['Ni58',0.0048423779739], + ['Ni60',0.0018652753260999999], + ['Ni61',8.108222689999999e-05], + ['Ni62',0.00025852561950000003], + ['Ni64',6.58388536e-05]]) +# Material Name: Duralumin base and top (2.78 g/cm3) +m4 = mcdc.material(nuclides=[ + ['Al27',0.058077], + ['Mg24',0.000815721732], + ['Mg25',0.00010352663999999999], + ['Mg26',0.00011395162799999999], + ['Mn55',0.00018284], + ['Cu63',0.0007834003500000001], + ['Cu65',0.00034949965000000003]]) +# Material Name: Duralumin top cylindrical shell (0.417 g/cm3) +m5 = mcdc.material(nuclides=[ + ['Al27',0.0087115], + ['Mg24',0.00012235825980000002], + ['Mg25',1.5528996000000002e-05], + ['Mg26',1.70927442e-05], + ['Mn55',2.7426e-05], + ['Cu63',0.00011750659499999998], + ['Cu65',5.2423405e-05]]) +# Material Name: Duralumin bottom cylindrical shell (1.8155 g/cm3) +m6 = mcdc.material(nuclides=[ + ['Al27',0.037928], + ['Mg24',0.0005327218725], + ['Mg25',6.760995e-05], + ['Mg26',7.44181775e-05], + ['Mn55',0.00011941], + ['Cu63',0.00051158553], + ['Cu65',0.00022823446999999998]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-17.345, bc='vacuum') +s2 = mcdc.surface('plane-z', z=-2.45, bc='interface') +s3 = mcdc.surface('plane-z', z=-2.43, bc='interface') +s4 = mcdc.surface('plane-z', z=-2.25, bc='interface') +s5 = mcdc.surface('plane-z', z=-1.98, bc='interface') +s6 = mcdc.surface('plane-z', z=-1.94, bc='interface') +s7 = mcdc.surface('plane-z', z=-1.49, bc='interface') +s8 = mcdc.surface('plane-z', z=-1.45, bc='interface') +s9 = mcdc.surface('plane-z', z=-1.0, bc='interface') +s10 = mcdc.surface('plane-z', z=-0.96, bc='interface') +s11 = mcdc.surface('plane-z', z=-0.51, bc='interface') +s12 = mcdc.surface('plane-z', z=-0.47, bc='interface') +s13 = mcdc.surface('plane-z', z=-0.02, bc='interface') +s14 = mcdc.surface('plane-z', z=0.0, bc='interface') +s15 = mcdc.surface('plane-z', z=0.01, bc='interface') +s16 = mcdc.surface('plane-z', z=0.03, bc='interface') +s17 = mcdc.surface('plane-z', z=0.48, bc='interface') +s18 = mcdc.surface('plane-z', z=0.52, bc='interface') +s19 = mcdc.surface('plane-z', z=0.97, bc='interface') +s20 = mcdc.surface('plane-z', z=1.01, bc='interface') +s21 = mcdc.surface('plane-z', z=1.46, bc='interface') +s22 = mcdc.surface('plane-z', z=1.5, bc='interface') +s23 = mcdc.surface('plane-z', z=1.95, bc='interface') +s24 = mcdc.surface('plane-z', z=1.99, bc='interface') +s25 = mcdc.surface('plane-z', z=2.26, bc='interface') +s26 = mcdc.surface('plane-z', z=2.44, bc='interface') +s27 = mcdc.surface('plane-z', z=2.46, bc='interface') +s28 = mcdc.surface('plane-z', z=2.48, bc='interface') +s29 = mcdc.surface('plane-z', z=17.375, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.995, bc='vacuum') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.263, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.063, bc='interface') +s33 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=5.995, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s30, fill=m2) +c2 = mcdc.cell(+s28 & -s29 & -s30, fill=m2) +c3 = mcdc.cell(+s2 & -s4 & -s30 & +s31, fill=m4) +c4 = mcdc.cell(+s25 & -s28 & -s30 & +s31, fill=m4) +c6 = mcdc.cell(+s15 & -s28 & -s31 & +s32, fill=m5) +c7 = mcdc.cell(+s2 & -s14 & -s31 & +s32, fill=m6) +c8 = mcdc.cell(+s2 & -s3 & -s33, fill=m3) +c9 = mcdc.cell(+s5 & -s6 & -s33, fill=m3) +c10 = mcdc.cell(+s7 & -s8 & -s33, fill=m3) +c11 = mcdc.cell(+s9 & -s10 & -s33, fill=m3) +c12 = mcdc.cell(+s11 & -s12 & -s33, fill=m3) +c13 = mcdc.cell(+s13 & -s14 & -s33, fill=m3) +c14 = mcdc.cell(+s15 & -s16 & -s33, fill=m3) +c15 = mcdc.cell(+s17 & -s18 & -s33, fill=m3) +c16 = mcdc.cell(+s19 & -s20 & -s33, fill=m3) +c17 = mcdc.cell(+s21 & -s22 & -s33, fill=m3) +c18 = mcdc.cell(+s23 & -s24 & -s33, fill=m3) +c19 = mcdc.cell(+s26 & -s27 & -s33, fill=m3) +c20 = mcdc.cell(+s2 & -s14 & +s33 & -s32, fill=m3) +c21 = mcdc.cell(+s15 & -s27 & +s33 & -s32, fill=m3) +c22 = mcdc.cell(+s3 & -s5 & -s33, fill=m1) +c23 = mcdc.cell(+s6 & -s7 & -s33, fill=m1) +c24 = mcdc.cell(+s8 & -s9 & -s33, fill=m1) +c25 = mcdc.cell(+s10 & -s11 & -s33, fill=m1) +c26 = mcdc.cell(+s12 & -s13 & -s33, fill=m1) +c27 = mcdc.cell(+s16 & -s17 & -s33, fill=m1) +c28 = mcdc.cell(+s18 & -s19 & -s33, fill=m1) +c29 = mcdc.cell(+s20 & -s21 & -s33, fill=m1) +c30 = mcdc.cell(+s22 & -s23 & -s33, fill=m1) +c31 = mcdc.cell(+s24 & -s26 & -s33, fill=m1) +c32 = mcdc.cell(+s14 & -s15 & -s31, fill=mvoid) +c33 = mcdc.cell(+s4 & -s25 & +s31 & -s30, fill=mvoid) +c34 = mcdc.cell(+s27 & -s28 & -s30, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-0.6,0.6], y=[-0.6,0.6], z=[5.17,6.17], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-021/mcdc/pu-met-fast-021_case-2.py b/icsbep/openmc/pu-met-fast-021/mcdc/pu-met-fast-021_case-2.py new file mode 100644 index 0000000..0de22aa --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/mcdc/pu-met-fast-021_case-2.py @@ -0,0 +1,170 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.044422], + ['Pu240',0.0021326], + ['C0',0.00019515], + ['Fe54',4.7895683500000004e-06], + ['Fe56',7.518598022e-05], + ['Fe57',1.7363721699999999e-06], + ['Fe58',2.3107926000000002e-07]]) +# Material Name: Berylium-oxide Reflector +# S(a,b): c_Be_in_BeO (Not Implemented) +# S(a,b): c_O_in_BeO (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.069041], + ['O16',0.069014833461], + ['O17',2.6166539e-05]]) +# Material Name: Steel Cover +m3 = mcdc.material(nuclides=[ + ['Fe54',0.002997316], + ['Fe56',0.047051451200000004], + ['Fe57',0.0010866232], + ['Fe58',0.0001446096], + ['C0',0.00034757000000000006], + ['Si28',0.0008225504010800002], + ['Si29',4.1766762459999996e-05], + ['Si30',2.7532836460000002e-05], + ['Ti46',5.0353049999999994e-05], + ['Ti47',4.5409295999999995e-05], + ['Ti48',0.00044994264799999995], + ['Ti49',3.3019394e-05], + ['Ti50',3.1615612e-05], + ['Cr50',0.0006279394], + ['Cr52',0.01210918628], + ['Cr53',0.00137308452], + ['Cr54',0.0003417898], + ['Mn55',0.0015198000000000002], + ['Ni58',0.0048423779739], + ['Ni60',0.0018652753260999999], + ['Ni61',8.108222689999999e-05], + ['Ni62',0.00025852561950000003], + ['Ni64',6.58388536e-05]]) +# Material Name: Duralumin base and top (2.78 g/cm3) +m4 = mcdc.material(nuclides=[ + ['Al27',0.058077], + ['Mg24',0.000815721732], + ['Mg25',0.00010352663999999999], + ['Mg26',0.00011395162799999999], + ['Mn55',0.00018284], + ['Cu63',0.0007834003500000001], + ['Cu65',0.00034949965000000003]]) +# Material Name: Duralumin top cylindrical shell (0.417 g/cm3) +m5 = mcdc.material(nuclides=[ + ['Al27',0.0087115], + ['Mg24',0.00012235825980000002], + ['Mg25',1.5528996000000002e-05], + ['Mg26',1.70927442e-05], + ['Mn55',2.7426e-05], + ['Cu63',0.00011750659499999998], + ['Cu65',5.2423405e-05]]) +# Material Name: Duralumin bottom cylindrical shell (1.8155 g/cm3) +m6 = mcdc.material(nuclides=[ + ['Al27',0.037928], + ['Mg24',0.0005327218725], + ['Mg25',6.760995e-05], + ['Mg26',7.44181775e-05], + ['Mn55',0.00011941], + ['Cu63',0.00051158553], + ['Cu65',0.00022823446999999998]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-z', z=-17.51, bc='vacuum') +s2 = mcdc.surface('plane-z', z=-2.57, bc='interface') +s3 = mcdc.surface('plane-z', z=-2.55, bc='interface') +s4 = mcdc.surface('plane-z', z=-2.37, bc='interface') +s5 = mcdc.surface('plane-z', z=-2.1, bc='interface') +s6 = mcdc.surface('plane-z', z=-2.06, bc='interface') +s7 = mcdc.surface('plane-z', z=-1.61, bc='interface') +s8 = mcdc.surface('plane-z', z=-1.57, bc='interface') +s9 = mcdc.surface('plane-z', z=-1.12, bc='interface') +s10 = mcdc.surface('plane-z', z=-1.08, bc='interface') +s11 = mcdc.surface('plane-z', z=-0.63, bc='interface') +s12 = mcdc.surface('plane-z', z=-0.59, bc='interface') +s13 = mcdc.surface('plane-z', z=-0.14, bc='interface') +s14 = mcdc.surface('plane-z', z=-0.12, bc='interface') +s15 = mcdc.surface('plane-z', z=0.12, bc='interface') +s16 = mcdc.surface('plane-z', z=0.14, bc='interface') +s17 = mcdc.surface('plane-z', z=0.59, bc='interface') +s18 = mcdc.surface('plane-z', z=0.63, bc='interface') +s19 = mcdc.surface('plane-z', z=1.08, bc='interface') +s20 = mcdc.surface('plane-z', z=1.12, bc='interface') +s21 = mcdc.surface('plane-z', z=1.57, bc='interface') +s22 = mcdc.surface('plane-z', z=1.61, bc='interface') +s23 = mcdc.surface('plane-z', z=2.06, bc='interface') +s24 = mcdc.surface('plane-z', z=2.1, bc='interface') +s25 = mcdc.surface('plane-z', z=2.37, bc='interface') +s26 = mcdc.surface('plane-z', z=2.55, bc='interface') +s27 = mcdc.surface('plane-z', z=2.57, bc='interface') +s28 = mcdc.surface('plane-z', z=2.59, bc='interface') +s29 = mcdc.surface('plane-z', z=17.51, bc='vacuum') +s30 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=9.995, bc='vacuum') +s31 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.263, bc='interface') +s32 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=6.063, bc='interface') +s33 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=5.995, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(+s1 & -s2 & -s30, fill=m2) +c2 = mcdc.cell(+s28 & -s29 & -s30, fill=m2) +c3 = mcdc.cell(+s2 & -s4 & -s30 & +s31, fill=m4) +c4 = mcdc.cell(+s25 & -s28 & -s30 & +s31, fill=m4) +c6 = mcdc.cell(+s15 & -s28 & -s31 & +s32, fill=m5) +c7 = mcdc.cell(+s2 & -s14 & -s31 & +s32, fill=m6) +c8 = mcdc.cell(+s2 & -s3 & -s33, fill=m3) +c9 = mcdc.cell(+s5 & -s6 & -s33, fill=m3) +c10 = mcdc.cell(+s7 & -s8 & -s33, fill=m3) +c11 = mcdc.cell(+s9 & -s10 & -s33, fill=m3) +c12 = mcdc.cell(+s11 & -s12 & -s33, fill=m3) +c13 = mcdc.cell(+s13 & -s14 & -s33, fill=m3) +c14 = mcdc.cell(+s15 & -s16 & -s33, fill=m3) +c15 = mcdc.cell(+s17 & -s18 & -s33, fill=m3) +c16 = mcdc.cell(+s19 & -s20 & -s33, fill=m3) +c17 = mcdc.cell(+s21 & -s22 & -s33, fill=m3) +c18 = mcdc.cell(+s23 & -s24 & -s33, fill=m3) +c19 = mcdc.cell(+s26 & -s27 & -s33, fill=m3) +c20 = mcdc.cell(+s2 & -s14 & +s33 & -s32, fill=m3) +c21 = mcdc.cell(+s15 & -s27 & +s33 & -s32, fill=m3) +c22 = mcdc.cell(+s3 & -s5 & -s33, fill=m1) +c23 = mcdc.cell(+s6 & -s7 & -s33, fill=m1) +c24 = mcdc.cell(+s8 & -s9 & -s33, fill=m1) +c25 = mcdc.cell(+s10 & -s11 & -s33, fill=m1) +c26 = mcdc.cell(+s12 & -s13 & -s33, fill=m1) +c27 = mcdc.cell(+s16 & -s17 & -s33, fill=m1) +c28 = mcdc.cell(+s18 & -s19 & -s33, fill=m1) +c29 = mcdc.cell(+s20 & -s21 & -s33, fill=m1) +c30 = mcdc.cell(+s22 & -s23 & -s33, fill=m1) +c31 = mcdc.cell(+s24 & -s26 & -s33, fill=m1) +c32 = mcdc.cell(+s14 & -s15 & -s31, fill=mvoid) +c33 = mcdc.cell(+s4 & -s25 & +s31 & -s30, fill=mvoid) +c34 = mcdc.cell(+s27 & -s28 & -s30, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[0.0,1.0], y=[0.0,1.0], z=[0.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-021/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..52a0667 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-1/generate_materials.py @@ -0,0 +1,62 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.4422e-02) +mat.add_nuclide('Pu240', 2.1326e-03) +mat.add_nuclide('Pu241', 9.2538e-05) +mat.add_element('C', 1.9515e-04) +mat.add_element('Fe', 8.1943e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Berylium Reflector" +mat.set_density('sum') +mat.add_element('Be', 1.2099e-01) +mat.add_element('O', 1.0449e-03) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel Cover" +mat.set_density('sum') +mat.add_element('Fe', 5.1280e-02) +mat.add_element('C', 3.4757e-04) +mat.add_element('Si', 8.9185e-04) +mat.add_element('Ti', 6.1034e-04) +mat.add_element('Cr', 1.4452e-02) +mat.add_element('Mn', 1.5198e-03) +mat.add_element('Ni', 7.1131e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Duralumin base and top (2.78 g/cm3)" +mat.set_density('sum') +mat.add_element('Al', 5.8077e-02) +mat.add_element('Mg', 1.0332e-03) +mat.add_element('Mn', 1.8284e-04) +mat.add_element('Cu', 1.1329e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Duralumin top cylindrical shell (0.417 g/cm3)" +mat.set_density('sum') +mat.add_element('Al', 8.7115e-03) +mat.add_element('Mg', 1.5498e-04) +mat.add_element('Mn', 2.7426e-05) +mat.add_element('Cu', 1.6993e-04) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Duralumin bottom cylindrical shell (1.8155 g/cm3)" +mat.set_density('sum') +mat.add_element('Al', 3.7928e-02) +mat.add_element('Mg', 6.7475e-04) +mat.add_element('Mn', 1.1941e-04) +mat.add_element('Cu', 7.3982e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-021/openmc/case-1/geometry.xml new file mode 100644 index 0000000..2f20143 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-1/geometry.xml @@ -0,0 +1,101 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-021/openmc/case-1/materials.xml new file mode 100644 index 0000000..87aaba0 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-1/materials.xml @@ -0,0 +1,77 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-021/openmc/case-1/settings.xml new file mode 100644 index 0000000..cf74331 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -.6 -.6 5.17 .6 .6 6.17 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-021/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..fd8e8f4 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-2/generate_materials.py @@ -0,0 +1,63 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.4422e-02) +mat.add_nuclide('Pu240', 2.1326e-03) +mat.add_nuclide('Pu241', 9.2538e-05) +mat.add_element('C', 1.9515e-04) +mat.add_element('Fe', 8.1943e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Berylium-oxide Reflector" +mat.set_density('sum') +mat.add_element('Be', 6.9041e-02) +mat.add_element('O', 6.9041e-02) +mat.add_s_alpha_beta('c_Be_in_BeO') +mat.add_s_alpha_beta('c_O_in_BeO') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel Cover" +mat.set_density('sum') +mat.add_element('Fe', 5.1280e-02) +mat.add_element('C', 3.4757e-04) +mat.add_element('Si', 8.9185e-04) +mat.add_element('Ti', 6.1034e-04) +mat.add_element('Cr', 1.4452e-02) +mat.add_element('Mn', 1.5198e-03) +mat.add_element('Ni', 7.1131e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Duralumin base and top (2.78 g/cm3)" +mat.set_density('sum') +mat.add_element('Al', 5.8077e-02) +mat.add_element('Mg', 1.0332e-03) +mat.add_element('Mn', 1.8284e-04) +mat.add_element('Cu', 1.1329e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Duralumin top cylindrical shell (0.417 g/cm3)" +mat.set_density('sum') +mat.add_element('Al', 8.7115e-03) +mat.add_element('Mg', 1.5498e-04) +mat.add_element('Mn', 2.7426e-05) +mat.add_element('Cu', 1.6993e-04) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Duralumin bottom cylindrical shell (1.8155 g/cm3)" +mat.set_density('sum') +mat.add_element('Al', 3.7928e-02) +mat.add_element('Mg', 6.7475e-04) +mat.add_element('Mn', 1.1941e-04) +mat.add_element('Cu', 7.3982e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-021/openmc/case-2/geometry.xml new file mode 100644 index 0000000..22b4c3a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-2/geometry.xml @@ -0,0 +1,101 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-021/openmc/case-2/materials.xml new file mode 100644 index 0000000..f9bd9ba --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-2/materials.xml @@ -0,0 +1,78 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-021/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-021/openmc/case-2/settings.xml new file mode 100644 index 0000000..12ff676 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-021/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + 0 0 0 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-022/mcdc/pu-met-fast-022_case-1.py b/icsbep/openmc/pu-met-fast-022/mcdc/pu-met-fast-022_case-1.py new file mode 100644 index 0000000..a7c54fd --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/mcdc/pu-met-fast-022_case-1.py @@ -0,0 +1,151 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036826], + ['Pu240',0.0006732000000000001], + ['Ga69',0.001322376], + ['Ga71',0.000877624], + ['Fe54',8.600333e-06], + ['Fe56',0.00013500683560000002], + ['Fe57',3.1178966e-06], + ['Fe58',4.1493480000000007e-07], + ['C0',0.00030406], + ['Ni58',0.0010703050217999999], + ['Ni60',0.00041227957819999996], + ['Ni61',1.79215078e-05], + ['Ni62',5.714160900000001e-05], + ['Ni64',1.45522832e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.0013292283119999998], + ['Ga71',0.000882171688], + ['Fe54',7.593824000000001e-06], + ['Fe56',0.0001192067968], + ['Fe57',2.7530048e-06], + ['Fe58',3.6637440000000004e-07], + ['C0',0.00030205], + ['Ni58',0.0013159264769999996], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.00131876952], + ['Ga71',0.0008752304800000001], + ['Fe54',7.5786269999999994e-06], + ['Fe56',0.0001189682364], + ['Fe57',2.7474954000000006e-06], + ['Fe58',3.6564120000000005e-07], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.13406336e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.0013292884199999997], + ['Ga71',0.00088221158], + ['Fe54',8.5436365e-06], + ['Fe56',0.0001341168218], + ['Fe57',3.0973423e-06], + ['Fe58',4.121994e-07], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999997e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036471], + ['Pu240',0.0006666500000000001], + ['Ga69',0.001301698848], + ['Ga71',0.0008639011520000001], + ['Fe54',8.516749500000001e-06], + ['Fe56',0.0001336947534], + ['Fe57',3.0875949000000004e-06], + ['Fe58',4.1090220000000005e-07], + ['C0',0.0003011], + ['Ni58',0.0013421360835], + ['Ni60',0.0005169884165], + ['Ni61',2.24731285e-05], + ['Ni62',7.165416750000001e-05], + ['Ni64',1.8248204000000004e-05]]) +# Material Name: Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['Pu239',0.036728], + ['Pu240',0.00067147], + ['Ga69',0.001326823992], + ['Ga71',0.000880576008], + ['Fe54',8.578122e-06], + ['Fe56',0.0001346581704], + ['Fe57',3.1098444000000004e-06], + ['Fe58',4.1386320000000004e-07], + ['C0',0.00030328], + ['Ni58',0.0011227242347999998], + ['Ni60',0.00043247136519999993], + ['Ni61',1.87992308e-05], + ['Ni62',5.994017400000001e-05], + ['Ni64',1.52649952e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.67, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-022/mcdc/pu-met-fast-022_case-2.py b/icsbep/openmc/pu-met-fast-022/mcdc/pu-met-fast-022_case-2.py new file mode 100644 index 0000000..90c3b96 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/mcdc/pu-met-fast-022_case-2.py @@ -0,0 +1,56 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 98% Pu-239 in delta phase +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036623], + ['Pu240',0.0006695099999999999], + ['Ga69',0.0013211137319999997], + ['Ga71',0.000876786268], + ['Fe54',8.327371500000001e-06], + ['Fe56',0.00013072192380000002], + ['Fe57',3.0189393000000003e-06], + ['Fe58',4.0176539999999997e-07], + ['C0',0.00029311], + ['Ni58',0.0012678641855999998], + ['Ni60',0.0004883790144], + ['Ni61',2.1229497600000002e-05], + ['Ni62',6.7688928e-05], + ['Ni64',1.72383744e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.67, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-022/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..6547516 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-1/generate_materials.py @@ -0,0 +1,71 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6826e-02) +mat.add_nuclide('Pu240', 6.7320e-04) +mat.add_element('Ga', 2.2000e-03) +mat.add_element('Fe', 1.4714e-04) +mat.add_element('C', 3.0406e-04) +mat.add_element('Ni', 1.5722e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.2114e-03) +mat.add_element('Fe', 1.2992e-04) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.1940e-03) +mat.add_element('Fe', 1.2966e-04) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.2115e-03) +mat.add_element('Fe', 1.4617e-04) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6471e-02) +mat.add_nuclide('Pu240', 6.6665e-04) +mat.add_element('Ga', 2.1656e-03) +mat.add_element('Fe', 1.4571e-04) +mat.add_element('C', 3.0110e-04) +mat.add_element('Ni', 1.9715e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Layer 6" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6728e-02) +mat.add_nuclide('Pu240', 6.7147e-04) +mat.add_element('Ga', 2.2074e-03) +mat.add_element('Fe', 1.4676e-04) +mat.add_element('C', 3.0328e-04) +mat.add_element('Ni', 1.6492e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-022/openmc/case-1/geometry.xml new file mode 100644 index 0000000..fbf44fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-1/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-022/openmc/case-1/materials.xml new file mode 100644 index 0000000..65edcfe --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-1/materials.xml @@ -0,0 +1,105 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-022/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-022/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..937947a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-2/generate_materials.py @@ -0,0 +1,12 @@ +import openmc + +pu = openmc.Material(name = "98% Pu-239 in delta phase") +pu.add_nuclide('Pu239', 3.6623e-02) +pu.add_nuclide('Pu240', 6.6951e-04) +pu.add_element('Ga', 2.1979e-03) +pu.add_element('Fe', 1.4247e-04) +pu.add_element('C', 2.9311e-04) +pu.add_element('Ni', 1.8624e-03) + +materials = openmc.Materials([pu]) +materials.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-022/openmc/case-2/geometry.xml new file mode 100644 index 0000000..7ea1442 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-022/openmc/case-2/materials.xml new file mode 100644 index 0000000..85b5ec9 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-2/materials.xml @@ -0,0 +1,20 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-022/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-022/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-022/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-023/mcdc/pu-met-fast-023_case-1.py b/icsbep/openmc/pu-met-fast-023/mcdc/pu-met-fast-023_case-1.py new file mode 100644 index 0000000..16ae3f5 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/mcdc/pu-met-fast-023_case-1.py @@ -0,0 +1,138 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 98% Pu-239 in delta phase, layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036825], + ['Pu240',0.00067318], + ['Ga69',0.0013223158919999998], + ['Ga71',0.0008775841079999999], + ['Fe54',8.599748500000001e-06], + ['Fe56',0.0001349976602], + ['Fe57',3.1176847000000002e-06], + ['Fe58',4.149066000000001e-07], + ['C0',0.00030405], + ['Ni58',0.0010703050217999999], + ['Ni60',0.00041227957819999996], + ['Ni61',1.79215078e-05], + ['Ni62',5.7141609e-05], + ['Ni64',1.45522832e-05]]) +# Material Name: 98% Pu-239 in delta phase, layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.0013292283119999998], + ['Ga71',0.000882171688], + ['Fe54',7.593824000000001e-06], + ['Fe56',0.0001192067968], + ['Fe57',2.7530048e-06], + ['Fe58',3.6637440000000004e-07], + ['C0',0.00030205], + ['Ni58',0.0013159264769999996], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: 98% Pu-239 in delta phase, layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.00131876952], + ['Ga71',0.0008752304800000001], + ['Fe54',7.5786269999999994e-06], + ['Fe56',0.0001189682364], + ['Fe57',2.7474954000000006e-06], + ['Fe58',3.6564120000000005e-07], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.13406336e-05]]) +# Material Name: 98% Pu-239 in delta phase, layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.0013292884199999997], + ['Ga71',0.00088221158], + ['Fe54',8.5436365e-06], + ['Fe56',0.0001341168218], + ['Fe57',3.0973423e-06], + ['Fe58',4.121994e-07], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999997e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: 98% Pu-239 in delta phase, layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036471], + ['Pu240',0.0006666500000000001], + ['Ga69',0.001301698848], + ['Ga71',0.0008639011520000001], + ['Fe54',8.516749500000001e-06], + ['Fe56',0.0001336947534], + ['Fe57',3.0875949000000004e-06], + ['Fe58',4.1090220000000005e-07], + ['C0',0.0003011], + ['Ni58',0.0013421360835], + ['Ni60',0.0005169884165], + ['Ni61',2.24731285e-05], + ['Ni62',7.165416750000001e-05], + ['Ni64',1.8248204000000004e-05]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m6 = mcdc.material(nuclides=[ + ['C0',0.091842]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.715, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-023/mcdc/pu-met-fast-023_case-2.py b/icsbep/openmc/pu-met-fast-023/mcdc/pu-met-fast-023_case-2.py new file mode 100644 index 0000000..dc46177 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/mcdc/pu-met-fast-023_case-2.py @@ -0,0 +1,62 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 98% Pu-239 in delta phase +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036603], + ['Pu240',0.0006691299999999999], + ['Ga69',0.0013197312479999999], + ['Ga71',0.0008758687520000001], + ['Fe54',8.233267000000001e-06], + ['Fe56',0.0001292446844], + ['Fe57',2.9848234e-06], + ['Fe58',3.9722519999999997e-07], + ['C0',0.00028927], + ['Ni58',0.0013264103195999998], + ['Ni60',0.0005109308804], + ['Ni61',2.2209811600000002e-05], + ['Ni62',7.081459800000001e-05], + ['Ni64',1.80343904e-05]]) +# Material Name: c_Graphite +# S(a,b): c_Graphite (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.091842]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.715, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-023/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..3175d9c --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-1/generate_materials.py @@ -0,0 +1,67 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "98% Pu-239 in delta phase, layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6825e-02) +mat.add_nuclide('Pu240', 6.7318e-04) +mat.add_element('Ga', 2.1999e-03) +mat.add_element('Fe', 1.4713e-04) +mat.add_element('C', 3.0405e-04) +mat.add_element('Ni', 1.5722e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "98% Pu-239 in delta phase, layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.2114e-03) +mat.add_element('Fe', 1.2992e-04) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "98% Pu-239 in delta phase, layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.1940e-03) +mat.add_element('Fe', 1.2966e-04) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "98% Pu-239 in delta phase, layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.2115e-03) +mat.add_element('Fe', 1.4617e-04) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "98% Pu-239 in delta phase, layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6471e-02) +mat.add_nuclide('Pu240', 6.6665e-04) +mat.add_element('Ga', 2.1656e-03) +mat.add_element('Fe', 1.4571e-04) +mat.add_element('C', 3.0110e-04) +mat.add_element('Ni', 1.9715e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 9.1842e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-023/openmc/case-1/geometry.xml new file mode 100644 index 0000000..d8c4a78 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-1/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-023/openmc/case-1/materials.xml new file mode 100644 index 0000000..39f61b1 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-1/materials.xml @@ -0,0 +1,93 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-023/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-023/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..569435d --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-2/generate_materials.py @@ -0,0 +1,23 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6603e-02) +mat.add_nuclide('Pu240', 6.6913e-04) +mat.add_element('Ga', 2.1956e-03) +mat.add_element('Fe', 1.4086e-04) +mat.add_element('C', 2.8927e-04) +mat.add_element('Ni', 1.9484e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "c_Graphite" +mat.set_density('sum') +mat.add_element('C', 9.1842e-02) +mat.add_s_alpha_beta('c_Graphite') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-023/openmc/case-2/geometry.xml new file mode 100644 index 0000000..22cd7e7 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-023/openmc/case-2/materials.xml new file mode 100644 index 0000000..690288c --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-2/materials.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-023/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-023/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-023/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-024/mcdc/pu-met-fast-024_case-1.py b/icsbep/openmc/pu-met-fast-024/mcdc/pu-met-fast-024_case-1.py new file mode 100644 index 0000000..2216491 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/mcdc/pu-met-fast-024_case-1.py @@ -0,0 +1,156 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.03618], + ['Pu240',0.00066139], + ['Ga69',0.0012914203799999997], + ['Ga71',0.0008570796199999998], + ['Fe54',9.388239e-06], + ['Fe56',0.0001473752748], + ['Fe57',3.4035378000000004e-06], + ['Fe58',4.5294839999999996e-07], + ['C0',0.00029873], + ['Ni58',0.0028951063262999998], + ['Ni60',0.0011151897736999998], + ['Ni61',4.84765273e-05], + ['Ni62',0.0001545643815], + ['Ni64',3.93629912e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036826], + ['Pu240',0.0006732000000000001], + ['Ga69',0.001322376], + ['Ga71',0.000877624], + ['Fe54',8.600333e-06], + ['Fe56',0.00013500683560000002], + ['Fe57',3.1178966e-06], + ['Fe58',4.1493480000000007e-07], + ['C0',0.00030406], + ['Ni58',0.0010703050217999999], + ['Ni60',0.00041227957819999996], + ['Ni61',1.79215078e-05], + ['Ni62',5.714160900000001e-05], + ['Ni64',1.45522832e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.0013292283119999998], + ['Ga71',0.000882171688], + ['Fe54',7.593824000000001e-06], + ['Fe56',0.0001192067968], + ['Fe57',2.7530048e-06], + ['Fe58',3.6637440000000004e-07], + ['C0',0.00030205], + ['Ni58',0.0013159264769999996], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.00131876952], + ['Ga71',0.0008752304800000001], + ['Fe54',7.5786269999999994e-06], + ['Fe56',0.0001189682364], + ['Fe57',2.7474954000000006e-06], + ['Fe58',3.6564120000000005e-07], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.13406336e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.0013292884199999997], + ['Ga71',0.00088221158], + ['Fe54',8.5436365e-06], + ['Fe56',0.0001341168218], + ['Fe57',3.0973423e-06], + ['Fe58',4.121994e-07], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999997e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['Pu239',0.036616], + ['Pu240',0.0006693], + ['Ga69',0.0013068681359999998], + ['Ga71',0.000867331864], + ['Fe54',8.550066e-06], + ['Fe56',0.0001342177512], + ['Fe57',3.0996732e-06], + ['Fe58',4.1250959999999996e-07], + ['C0',0.0003023], + ['Ni58',0.0013475141586], + ['Ni60',0.0005190600414], + ['Ni61',2.25631806e-05], + ['Ni62',7.1941293e-05], + ['Ni64',1.83213264e-05]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m7 = mcdc.material(nuclides=[ + ['H1',0.077628], + ['C0',0.038814]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m6) +c7 = mcdc.cell(+s6 & -s7, fill=m7) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-024/mcdc/pu-met-fast-024_case-2.py b/icsbep/openmc/pu-met-fast-024/mcdc/pu-met-fast-024_case-2.py new file mode 100644 index 0000000..be0532f --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/mcdc/pu-met-fast-024_case-2.py @@ -0,0 +1,61 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 98% Pu-239 in delta phase +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.03662], + ['Pu240',0.0006694399999999999], + ['Ga69',0.001320091896], + ['Ga71',0.0008761081040000001], + ['Fe54',8.256647000000002e-06], + ['Fe56',0.0001296117004], + ['Fe57',2.9932994e-06], + ['Fe58',3.9835320000000003e-07], + ['C0',0.00028972], + ['Ni58',0.0013443826212], + ['Ni60',0.0005178537788], + ['Ni61',2.25107452e-05], + ['Ni62',7.1774106e-05], + ['Ni64',1.8278748800000003e-05]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['C0',0.038814], + ['H1',0.077628]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-024/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..f2319b3 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-1/generate_materials.py @@ -0,0 +1,79 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6180e-02) +mat.add_nuclide('Pu240', 6.6139e-04) +mat.add_element('Ga', 2.1485e-03) +mat.add_element('Fe', 1.6062e-04) +mat.add_element('C', 2.9873e-04) +mat.add_element('Ni', 4.2527e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6826e-02) +mat.add_nuclide('Pu240', 6.7320e-04) +mat.add_element('Ga', 2.2000e-03) +mat.add_element('Fe', 1.4714e-04) +mat.add_element('C', 3.0406e-04) +mat.add_element('Ni', 1.5722e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.2114e-03) +mat.add_element('Fe', 1.2992e-04) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.1940e-03) +mat.add_element('Fe', 1.2966e-04) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.2115e-03) +mat.add_element('Fe', 1.4617e-04) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Layer 6" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6616e-02) +mat.add_nuclide('Pu240', 6.6930e-04) +mat.add_element('Ga', 2.1742e-03) +mat.add_element('Fe', 1.4628e-04) +mat.add_element('C', 3.0230e-04) +mat.add_element('Ni', 1.9794e-03) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_nuclide('H1', 7.7628e-02) +mat.add_element('C', 3.8814e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-024/openmc/case-1/geometry.xml new file mode 100644 index 0000000..3244955 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-1/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-024/openmc/case-1/materials.xml new file mode 100644 index 0000000..28a8d9b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-1/materials.xml @@ -0,0 +1,111 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-024/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-024/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..5ce8c60 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-2/generate_materials.py @@ -0,0 +1,17 @@ +import openmc + +pu = openmc.Material(name = "98% Pu-239 in delta phase") +pu.add_nuclide('Pu239', 3.6620e-02) +pu.add_nuclide('Pu240', 6.6944e-04) +pu.add_element('Ga', 2.1962e-03) +pu.add_element('Fe', 1.4126e-04) +pu.add_element('C', 2.8972e-04) +pu.add_element('Ni', 1.9748e-03) + +ch2 = openmc.Material(name="Polyethylene") +ch2.add_element('C', 0.038814) +ch2.add_nuclide('H1', 0.077628) +ch2.add_s_alpha_beta('c_H_in_CH2') + +materials = openmc.Materials([pu, ch2]) +materials.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-024/openmc/case-2/geometry.xml new file mode 100644 index 0000000..8ea859e --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-024/openmc/case-2/materials.xml new file mode 100644 index 0000000..9aba744 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-2/materials.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-024/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-024/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-024/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-025/mcdc/pu-met-fast-025_case-1.py b/icsbep/openmc/pu-met-fast-025/mcdc/pu-met-fast-025_case-1.py new file mode 100644 index 0000000..9577248 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/mcdc/pu-met-fast-025_case-1.py @@ -0,0 +1,173 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036182], + ['Pu240',0.00066143], + ['Ga69',0.001291480488], + ['Ga71',0.0008571195120000001], + ['Fe54',9.388823500000002e-06], + ['Fe56',0.00014738445020000002], + ['Fe57',3.4037497000000004e-06], + ['Fe58',4.529766e-07], + ['C0',0.00029874], + ['Ni58',0.0028952424801], + ['Ni60',0.0011152422199000001], + ['Ni61',4.8478807100000005e-05], + ['Ni62',0.00015457165050000002], + ['Ni64',3.936484240000001e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036826], + ['Pu240',0.0006732000000000001], + ['Ga69',0.001322376], + ['Ga71',0.000877624], + ['Fe54',8.600333e-06], + ['Fe56',0.00013500683560000002], + ['Fe57',3.1178966e-06], + ['Fe58',4.1493480000000007e-07], + ['C0',0.00030406], + ['Ni58',0.0010703050217999999], + ['Ni60',0.00041227957819999996], + ['Ni61',1.79215078e-05], + ['Ni62',5.714160900000001e-05], + ['Ni64',1.45522832e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036711], + ['Pu240',0.00067117], + ['Ga69',0.0013340369519999997], + ['Ga71',0.0008853630479999999], + ['Fe54',7.6212955e-06], + ['Fe56',0.0001196380406], + ['Fe57',2.7629641000000003e-06], + ['Fe58',3.6769979999999995e-07], + ['C0',0.00030315], + ['Ni58',0.00132069186], + ['Ni60',0.00050872814], + ['Ni61',2.2114059999999996e-05], + ['Ni62',7.05093e-05], + ['Ni64',1.7956640000000003e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036632], + ['Pu240',0.0006695800000000001], + ['Ga69',0.0013230972959999995], + ['Ga71',0.0008781027039999999], + ['Fe54',7.6037605e-06], + ['Fe56',0.0001193627786], + ['Fe57',2.7566071000000003e-06], + ['Fe58',3.668538e-07], + ['C0',0.00022682000000000003], + ['Ni58',0.0015747548507999997], + ['Ni60',0.0006065927492], + ['Ni61',2.63681668e-05], + ['Ni62',8.407325400000001e-05], + ['Ni64',2.14109792e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036725], + ['Pu240',0.0006715000000000001], + ['Ga69',0.0013346981399999997], + ['Ga71',0.0008858018599999999], + ['Fe54',8.5787065e-06], + ['Fe56',0.0001346673458], + ['Fe57',3.1100563000000004e-06], + ['Fe58',4.1389139999999995e-07], + ['C0',0.00030329], + ['Ni58',0.0012734464914], + ['Ni60',0.0004905293086], + ['Ni61',2.13229694e-05], + ['Ni62',6.798695700000001e-05], + ['Ni64',1.73142736e-05]]) +# Material Name: Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['Pu239',0.036654], + ['Pu240',0.00066998], + ['Ga69',0.001308190512], + ['Ga71',0.0008682094880000001], + ['Fe54',8.5588335e-06], + ['Fe56',0.00013435538219999998], + ['Fe57',3.1028517e-06], + ['Fe58',4.129326e-07], + ['C0',0.00030261], + ['Ni58',0.0013488756966], + ['Ni60',0.0005195845034], + ['Ni61',2.2585978599999996e-05], + ['Ni62',7.2013983e-05], + ['Ni64',1.83398384e-05]]) +# Material Name: Steel reflector +m7 = mcdc.material(nuclides=[ + ['Fe54',0.00465010665], + ['Fe56',0.07299672978], + ['Fe57',0.0016858128300000002], + ['Fe58',0.00022435074], + ['C0',0.0011289], + ['Si28',0.000148425224024], + ['Si29',7.536609388e-06], + ['Si30',4.968166588e-06], + ['Cr50',1.1330891e-05], + ['Cr52',0.0002185049542], + ['Cr53',2.47767078e-05], + ['Cr54',6.167447000000001e-06], + ['Mn55',0.00032909], + ['Ni58',0.00015728486976], + ['Ni60',6.0585850240000005e-05], + ['Ni61',2.6336249599999996e-06], + ['Ni62',8.3971488e-06], + ['Ni64',2.13850624e-06], + ['Cu63',0.00014755227], + ['Cu65',6.582773e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m5) +c6 = mcdc.cell(+s5 & -s6, fill=m6) +c7 = mcdc.cell(+s6 & -s7, fill=m7) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-025/mcdc/pu-met-fast-025_case-2.py b/icsbep/openmc/pu-met-fast-025/mcdc/pu-met-fast-025_case-2.py new file mode 100644 index 0000000..4bf8de4 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/mcdc/pu-met-fast-025_case-2.py @@ -0,0 +1,78 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: HEU +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036704], + ['Pu240',0.00067099], + ['Ga69',0.0013231574039999998], + ['Ga71',0.0008781425959999998], + ['Fe54',8.2759355e-06], + ['Fe56',0.0001299144886], + ['Fe57',3.0002921e-06], + ['Fe58',3.992838000000001e-07], + ['C0',0.00029038], + ['Ni58',0.0013475141586000003], + ['Ni60',0.0005190600414], + ['Ni61',2.25631806e-05], + ['Ni62',7.1941293e-05], + ['Ni64',1.83213264e-05]]) +# Material Name: Steel reflector +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00465010665], + ['Fe56',0.07299672978], + ['Fe57',0.0016858128300000002], + ['Fe58',0.00022435074], + ['C0',0.0011289], + ['Si28',0.000148425224024], + ['Si29',7.536609388e-06], + ['Si30',4.968166588e-06], + ['Cr50',1.1330891e-05], + ['Cr52',0.0002185049542], + ['Cr53',2.47767078e-05], + ['Cr54',6.167447000000001e-06], + ['Mn55',0.00032909], + ['Ni58',0.00015728486976], + ['Ni60',6.0585850240000005e-05], + ['Ni61',2.6336249599999996e-06], + ['Ni62',8.3971488e-06], + ['Ni64',2.13850624e-06], + ['Cu63',0.00014755227], + ['Cu65',6.582773e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-025/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..96771d8 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-1/generate_materials.py @@ -0,0 +1,83 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6182e-02) +mat.add_nuclide('Pu240', 6.6143e-04) +mat.add_element('Ga', 2.1486e-03) +mat.add_element('Fe', 1.6063e-04) +mat.add_element('C', 2.9874e-04) +mat.add_element('Ni', 4.2529e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6826e-02) +mat.add_nuclide('Pu240', 6.7320e-04) +mat.add_element('Ga', 2.2000e-03) +mat.add_element('Fe', 1.4714e-04) +mat.add_element('C', 3.0406e-04) +mat.add_element('Ni', 1.5722e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6711e-02) +mat.add_nuclide('Pu240', 6.7117e-04) +mat.add_element('Ga', 2.2194e-03) +mat.add_element('Fe', 1.3039e-04) +mat.add_element('C', 3.0315e-04) +mat.add_element('Ni', 1.9400e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6632e-02) +mat.add_nuclide('Pu240', 6.6958e-04) +mat.add_element('Ga', 2.2012e-03) +mat.add_element('Fe', 1.3009e-04) +mat.add_element('C', 2.2682e-04) +mat.add_element('Ni', 2.3132e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6725e-02) +mat.add_nuclide('Pu240', 6.7150e-04) +mat.add_element('Ga', 2.2205e-03) +mat.add_element('Fe', 1.4677e-04) +mat.add_element('C', 3.0329e-04) +mat.add_element('Ni', 1.8706e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Layer 6" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6654e-02) +mat.add_nuclide('Pu240', 6.6998e-04) +mat.add_element('Ga', 2.1764e-03) +mat.add_element('Fe', 1.4643e-04) +mat.add_element('C', 3.0261e-04) +mat.add_element('Ni', 1.9814e-03) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Steel reflector" +mat.set_density('sum') +mat.add_element('Fe', 7.9557e-02) +mat.add_element('C', 1.1289e-03) +mat.add_element('Si', 1.6093e-04) +mat.add_element('Cr', 2.6078e-04) +mat.add_element('Mn', 3.2909e-04) +mat.add_element('Ni', 2.3104e-04) +mat.add_element('Cu', 2.1338e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-025/openmc/case-1/geometry.xml new file mode 100644 index 0000000..58f7b61 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-1/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-025/openmc/case-1/materials.xml new file mode 100644 index 0000000..903a5ec --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-1/materials.xml @@ -0,0 +1,128 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-025/openmc/case-1/settings.xml new file mode 100644 index 0000000..ed10361 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-1/settings.xml @@ -0,0 +1,19 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-025/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..2b6f61a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-2/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "HEU" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6704e-02) +mat.add_nuclide('Pu240', 6.7099e-04) +mat.add_element('Ga', 2.2013e-03) +mat.add_element('Fe', 1.4159e-04) +mat.add_element('C', 2.9038e-04) +mat.add_element('Ni', 1.9794e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Steel reflector" +mat.set_density('sum') +mat.add_element('Fe', 7.9557e-02) +mat.add_element('C', 1.1289e-03) +mat.add_element('Si', 1.6093e-04) +mat.add_element('Cr', 2.6078e-04) +mat.add_element('Mn', 3.2909e-04) +mat.add_element('Ni', 2.3104e-04) +mat.add_element('Cu', 2.1338e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-025/openmc/case-2/geometry.xml new file mode 100644 index 0000000..f7f6358 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-025/openmc/case-2/materials.xml new file mode 100644 index 0000000..3593d51 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-2/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-025/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-025/openmc/case-2/settings.xml new file mode 100644 index 0000000..ed10361 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-025/openmc/case-2/settings.xml @@ -0,0 +1,19 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-026/mcdc/pu-met-fast-026_case-1.py b/icsbep/openmc/pu-met-fast-026/mcdc/pu-met-fast-026_case-1.py new file mode 100644 index 0000000..8dee3c5 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/mcdc/pu-met-fast-026_case-1.py @@ -0,0 +1,180 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 98% Pu-239 in delta phase +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.035272], + ['Pu240',0.00064479], + ['Ga69',0.0012590221679999998], + ['Ga71',0.0008355778319999999], + ['Fe54',9.1526855e-06], + ['Fe56',0.0001436775886], + ['Fe57',3.3181421e-06], + ['Fe58',4.415838e-07], + ['C0',0.00029123], + ['Ni58',0.0028224001971], + ['Ni60',0.0010871835029], + ['Ni61',4.72591141e-05], + ['Ni62',0.0001506827355], + ['Ni64',3.83744504e-05]]) +# Material Name: 98% Pu-239 in delta phase +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036826], + ['Pu240',0.0006732000000000001], + ['Ga69',0.001322376], + ['Ga71',0.000877624], + ['Fe54',8.600333e-06], + ['Fe56',0.00013500683560000002], + ['Fe57',3.1178966e-06], + ['Fe58',4.1493480000000007e-07], + ['C0',0.00030406], + ['Ni58',0.0010703050217999999], + ['Ni60',0.00041227957819999996], + ['Ni61',1.79215078e-05], + ['Ni62',5.714160900000001e-05], + ['Ni64',1.45522832e-05]]) +# Material Name: 98% Pu-239 in delta phase +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.0013292283119999998], + ['Ga71',0.000882171688], + ['Fe54',7.593824000000001e-06], + ['Fe56',0.0001192067968], + ['Fe57',2.7530048e-06], + ['Fe58',3.6637440000000004e-07], + ['C0',0.00030205], + ['Ni58',0.0013159264769999996], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: 98% Pu-239 in delta phase +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.00131876952], + ['Ga71',0.0008752304800000001], + ['Fe54',7.5786269999999994e-06], + ['Fe56',0.0001189682364], + ['Fe57',2.7474954000000006e-06], + ['Fe58',3.6564120000000005e-07], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.13406336e-05]]) +# Material Name: 98% Pu-239 in delta phase +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.0013292884199999997], + ['Ga71',0.00088221158], + ['Fe54',8.5436365e-06], + ['Fe56',0.0001341168218], + ['Fe57',3.0973423e-06], + ['Fe58',4.121994e-07], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999997e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Steel reflector 1 +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0046418652], + ['Fe56',0.07286735664], + ['Fe57',0.0016828250400000003], + ['Fe58',0.00022395312], + ['C0',0.0011269], + ['Si28',0.00014816698092000002], + ['Si29',7.523496540000001e-06], + ['Si30',4.95952254e-06], + ['Cr50',1.1310904e-05], + ['Cr52',0.0002181195248], + ['Cr53',2.4733003199999997e-05], + ['Cr54',6.156568e-06], + ['Mn55',0.0003285], + ['Ni58',0.00015700575447], + ['Ni60',6.0478335529999997e-05], + ['Ni61',2.6289513699999997e-06], + ['Ni62',8.38224735e-06], + ['Ni64',2.1347112800000003e-06], + ['Cu63',0.0001472895], + ['Cu65',6.57105e-05]]) +# Material Name: Steel reflector 2 +m7 = mcdc.material(nuclides=[ + ['Fe54',0.0046128155500000005], + ['Fe56',0.07241133926], + ['Fe57',0.0016722936100000002], + ['Fe58',0.00022255158000000004], + ['C0',0.0011199], + ['Si28',0.000147235461152], + ['Si29',7.476196624000001e-06], + ['Si30',4.928342224e-06], + ['Cr50',1.1240080500000001e-05], + ['Cr52',0.00021675376410000002], + ['Cr53',2.4578136900000004e-05], + ['Cr54',6.1180185e-06], + ['Mn55',0.00032645], + ['Ni58',0.00015601863941999998], + ['Ni60',6.0098100579999996e-05], + ['Ni61',2.61242282e-06], + ['Ni62',8.3295471e-06], + ['Ni64',2.12129008e-06], + ['Cu63',0.00014636980500000002], + ['Cu65',6.530019500000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.77, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.25, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-026/mcdc/pu-met-fast-026_case-2.py b/icsbep/openmc/pu-met-fast-026/mcdc/pu-met-fast-026_case-2.py new file mode 100644 index 0000000..0c3b4c4 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/mcdc/pu-met-fast-026_case-2.py @@ -0,0 +1,104 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: 98% Pu-239 in delta phase +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036603], + ['Pu240',0.00066917], + ['Ga69',0.001324960644], + ['Ga71',0.000879339356], + ['Fe54',8.128057e-06], + ['Fe56',0.0001275931124], + ['Fe57',2.9466814e-06], + ['Fe58',3.921492e-07], + ['C0',0.00028435], + ['Ni58',0.0013371664698], + ['Ni60',0.0005150741302], + ['Ni61',2.2389915799999998e-05], + ['Ni62',7.138884900000001e-05], + ['Ni64',1.8180635200000002e-05]]) +# Material Name: Steel reflector 1 +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0046418652], + ['Fe56',0.07286735664], + ['Fe57',0.0016828250400000003], + ['Fe58',0.00022395312], + ['C0',0.0011269], + ['Si28',0.00014816698092000002], + ['Si29',7.523496540000001e-06], + ['Si30',4.95952254e-06], + ['Cr50',1.1310904e-05], + ['Cr52',0.0002181195248], + ['Cr53',2.4733003199999997e-05], + ['Cr54',6.156568e-06], + ['Mn55',0.0003285], + ['Ni58',0.00015700575447], + ['Ni60',6.0478335529999997e-05], + ['Ni61',2.6289513699999997e-06], + ['Ni62',8.38224735e-06], + ['Ni64',2.1347112800000003e-06], + ['Cu63',0.0001472895], + ['Cu65',6.57105e-05]]) +# Material Name: Steel reflector 2 +m3 = mcdc.material(nuclides=[ + ['Fe54',0.0046128155500000005], + ['Fe56',0.07241133926], + ['Fe57',0.0016722936100000002], + ['Fe58',0.00022255158000000004], + ['C0',0.0011199], + ['Si28',0.000147235461152], + ['Si29',7.476196624000001e-06], + ['Si30',4.928342224e-06], + ['Cr50',1.1240080500000001e-05], + ['Cr52',0.00021675376410000002], + ['Cr53',2.4578136900000004e-05], + ['Cr54',6.1180185e-06], + ['Mn55',0.00032645], + ['Ni58',0.00015601863941999998], + ['Ni60',6.0098100579999996e-05], + ['Ni61',2.61242282e-06], + ['Ni62',8.3295471e-06], + ['Ni64',2.12129008e-06], + ['Cu63',0.00014636980500000002], + ['Cu65',6.530019500000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.77, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.25, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-026/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..b39e97f --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-1/generate_materials.py @@ -0,0 +1,84 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.5272e-02) +mat.add_nuclide('Pu240', 6.4479e-04) +mat.add_element('Ga', 2.0946e-03) +mat.add_element('Fe', 1.5659e-04) +mat.add_element('C', 2.9123e-04) +mat.add_element('Ni', 4.1459e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6826e-02) +mat.add_nuclide('Pu240', 6.7320e-04) +mat.add_element('Ga', 2.2000e-03) +mat.add_element('Fe', 1.4714e-04) +mat.add_element('C', 3.0406e-04) +mat.add_element('Ni', 1.5722e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.2114e-03) +mat.add_element('Fe', 1.2992e-04) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.1940e-03) +mat.add_element('Fe', 1.2966e-04) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.2115e-03) +mat.add_element('Fe', 1.4617e-04) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel reflector 1" +mat.set_density('sum') +mat.add_element('Fe', 7.9416e-02) +mat.add_element('C', 1.1269e-03) +mat.add_element('Si', 1.6065e-04) +mat.add_element('Cr', 2.6032e-04) +mat.add_element('Mn', 3.2850e-04) +mat.add_element('Ni', 2.3063e-04) +mat.add_element('Cu', 2.1300e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Steel reflector 2" +mat.set_density('sum') +mat.add_element('Fe', 7.8919e-02) +mat.add_element('C', 1.1199e-03) +mat.add_element('Si', 1.5964e-04) +mat.add_element('Cr', 2.5869e-04) +mat.add_element('Mn', 3.2645e-04) +mat.add_element('Ni', 2.2918e-04) +mat.add_element('Cu', 2.1167e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-026/openmc/case-1/geometry.xml new file mode 100644 index 0000000..cec5a63 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-1/geometry.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-026/openmc/case-1/materials.xml new file mode 100644 index 0000000..aa44ce9 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-1/materials.xml @@ -0,0 +1,134 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-026/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-026/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..618a721 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-2/generate_materials.py @@ -0,0 +1,40 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "98% Pu-239 in delta phase" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6603e-02) +mat.add_nuclide('Pu240', 6.6917e-04) +mat.add_element('Ga', 2.2043e-03) +mat.add_element('Fe', 1.3906e-04) +mat.add_element('C', 2.8435e-04) +mat.add_element('Ni', 1.9642e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Steel reflector 1" +mat.set_density('sum') +mat.add_element('Fe', 7.9416e-02) +mat.add_element('C', 1.1269e-03) +mat.add_element('Si', 1.6065e-04) +mat.add_element('Cr', 2.6032e-04) +mat.add_element('Mn', 3.2850e-04) +mat.add_element('Ni', 2.3063e-04) +mat.add_element('Cu', 2.1300e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Steel reflector 2" +mat.set_density('sum') +mat.add_element('Fe', 7.8919e-02) +mat.add_element('C', 1.1199e-03) +mat.add_element('Si', 1.5964e-04) +mat.add_element('Cr', 2.5869e-04) +mat.add_element('Mn', 3.2645e-04) +mat.add_element('Ni', 2.2918e-04) +mat.add_element('Cu', 2.1167e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-026/openmc/case-2/geometry.xml new file mode 100644 index 0000000..44cb9ec --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-026/openmc/case-2/materials.xml new file mode 100644 index 0000000..13b0822 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-2/materials.xml @@ -0,0 +1,66 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-026/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-026/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-026/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-029/mcdc/pu-met-fast-029_case-1.py b/icsbep/openmc/pu-met-fast-029/mcdc/pu-met-fast-029_case-1.py new file mode 100644 index 0000000..39e2955 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/mcdc/pu-met-fast-029_case-1.py @@ -0,0 +1,127 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.040892], + ['Pu240',0.0047716], + ['Fe54',1.7526817e-05], + ['Fe56',0.0002751335444], + ['Fe57',6.3540334000000005e-06], + ['Fe58',8.456052000000001e-07], + ['C0',0.0019577], + ['H1',0.0008189624349234001], + ['H2',1.275650766e-07], + ['N14',8.808715050700001e-05], + ['N15',3.23849493e-07], + ['O16',0.00013101032826], + ['O17',4.9671740000000006e-08]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.042276], + ['Pu240',0.004606], + ['Fe54',1.5509123e-05], + ['Fe56',0.00024346006359999994], + ['Fe57',5.6225546e-06], + ['Fe58',7.482587999999999e-07], + ['C0',0.0011053], + ['H1',0.00020007883486860005], + ['H2',3.11651314e-08], + ['N14',2.1520879200000002e-05], + ['N15',7.91208e-08], + ['O16',3.200786442e-05], + ['O17',1.213558e-08]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.041681], + ['Pu240',0.0047176], + ['Fe54',1.7743082e-05], + ['Fe56',0.0002785284424], + ['Fe57',6.4324363999999995e-06], + ['Fe58',8.560391999999999e-07], + ['C0',0.0011922], + ['H1',0.000275007163713], + ['H2',4.2836286999999996e-08], + ['N14',2.9579252856e-05], + ['N15',1.0874714400000001e-07], + ['O16',4.3994319831e-05], + ['O17',1.6680169000000002e-08]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.042431], + ['Pu240',0.0043997], + ['Fe54',1.665825e-05], + ['Fe56',0.0002614989], + ['Fe57',6.03915e-06], + ['Fe58',8.036999999999999e-07], + ['C0',0.0013956], + ['H1',0.0004330125521208], + ['H2',6.74478792e-08], + ['N14',4.6574769402e-05], + ['N15',1.71230598e-07], + ['O16',6.9270736437e-05], + ['O17',2.6263563000000002e-08]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.041407], + ['Pu240',0.0048168], + ['Fe54',2.12728775e-05], + ['Fe56',0.00033393868299999997], + ['Fe57',7.7121005e-06], + ['Fe58',1.026339e-06], + ['C0',0.0013617], + ['H1',0.0002608793643192], + ['H2',4.06356808e-08], + ['N14',2.8059838931000004e-05], + ['N15',1.03161069e-07], + ['O16',4.1733177129e-05], + ['O17',1.5822871e-08]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.8, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-029/mcdc/pu-met-fast-029_case-2.py b/icsbep/openmc/pu-met-fast-029/mcdc/pu-met-fast-029_case-2.py new file mode 100644 index 0000000..62ca13d --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/mcdc/pu-met-fast-029_case-2.py @@ -0,0 +1,54 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.041923], + ['Pu240',0.0046622], + ['Fe54',1.8291343e-05], + ['Fe56',0.0002871349676], + ['Fe57',6.6311986e-06], + ['Fe58',8.824908e-07], + ['C0',0.0012949], + ['H1',0.00030207294783120005], + ['H2',4.7052168800000004e-08], + ['N14',3.2490549570000004e-05], + ['N15',1.1945043e-07], + ['O16',4.8324678003e-05], + ['O17',1.8321997e-08]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.8, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-029/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..67597ef --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-1/generate_materials.py @@ -0,0 +1,70 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.0892e-02) +mat.add_nuclide('Pu240', 4.7716e-03) +mat.add_nuclide('Pu241', 8.9384e-04) +mat.add_element('Fe', 2.9986e-04) +mat.add_element('C', 1.9577e-03) +mat.add_element('H', 8.1909e-04) +mat.add_element('N', 8.8411e-05) +mat.add_element('O', 1.3106e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.2276e-02) +mat.add_nuclide('Pu240', 4.6060e-03) +mat.add_nuclide('Pu241', 6.7147e-04) +mat.add_element('Fe', 2.6534e-04) +mat.add_element('C', 1.1053e-03) +mat.add_element('H', 2.0011e-04) +mat.add_element('N', 2.1600e-05) +mat.add_element('O', 3.2020e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.1681e-02) +mat.add_nuclide('Pu240', 4.7176e-03) +mat.add_nuclide('Pu241', 7.4079e-04) +mat.add_element('Fe', 3.0356e-04) +mat.add_element('C', 1.1922e-03) +mat.add_element('H', 2.7505e-04) +mat.add_element('N', 2.9688e-05) +mat.add_element('O', 4.4011e-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.2431e-02) +mat.add_nuclide('Pu240', 4.3997e-03) +mat.add_nuclide('Pu241', 5.9425e-04) +mat.add_element('Fe', 2.8500e-04) +mat.add_element('C', 1.3956e-03) +mat.add_element('H', 4.3308e-04) +mat.add_element('N', 4.6746e-05) +mat.add_element('O', 6.9297e-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.1407e-02) +mat.add_nuclide('Pu240', 4.8168e-03) +mat.add_nuclide('Pu241', 8.4787e-04) +mat.add_element('Fe', 3.6395e-04) +mat.add_element('C', 1.3617e-03) +mat.add_element('H', 2.6092e-04) +mat.add_element('N', 2.8163e-05) +mat.add_element('O', 4.1749e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-029/openmc/case-1/geometry.xml new file mode 100644 index 0000000..169c272 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-1/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-029/openmc/case-1/materials.xml new file mode 100644 index 0000000..09b063e --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-1/materials.xml @@ -0,0 +1,88 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-029/openmc/case-1/settings.xml new file mode 100644 index 0000000..ed10361 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-1/settings.xml @@ -0,0 +1,19 @@ + + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-029/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..d050d1b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-2/generate_materials.py @@ -0,0 +1,17 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.1923e-02) +mat.add_nuclide('Pu240', 4.6622e-03) +mat.add_nuclide('Pu241', 7.3273e-04) +mat.add_element('Fe', 3.1294e-04) +mat.add_element('C', 1.2949e-03) +mat.add_element('H', 3.0212e-04) +mat.add_element('N', 3.2610e-05) +mat.add_element('O', 4.8343e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-029/openmc/case-2/geometry.xml new file mode 100644 index 0000000..412b569 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-029/openmc/case-2/materials.xml new file mode 100644 index 0000000..2afe7ac --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-2/materials.xml @@ -0,0 +1,20 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-029/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-029/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-029/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-032/mcdc/pu-met-fast-032_case-1.py b/icsbep/openmc/pu-met-fast-032/mcdc/pu-met-fast-032_case-1.py new file mode 100644 index 0000000..cfd1ac8 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/mcdc/pu-met-fast-032_case-1.py @@ -0,0 +1,133 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.041607], + ['Pu240',0.0048551], + ['Fe54',1.7833095e-05], + ['Fe56',0.000279941454], + ['Fe57',6.4650689999999995e-06], + ['Fe58',8.603819999999999e-07], + ['C0',0.001992], + ['H1',0.0008332902031692], + ['H2',1.2979683079999999e-07], + ['N14',8.9628483846e-05], + ['N15',3.29516154e-07], + ['O16',0.00013330945656], + ['O17',5.0543440000000006e-08]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.042276], + ['Pu240',0.004606], + ['Fe54',1.5509123e-05], + ['Fe56',0.00024346006359999994], + ['Fe57',5.6225546e-06], + ['Fe58',7.482587999999999e-07], + ['C0',0.0011053], + ['H1',0.00020007883486860005], + ['H2',3.11651314e-08], + ['N14',2.1520879200000002e-05], + ['N15',7.91208e-08], + ['O16',3.200786442e-05], + ['O17',1.213558e-08]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.041681], + ['Pu240',0.0047176], + ['Fe54',1.7743082e-05], + ['Fe56',0.0002785284424], + ['Fe57',6.4324363999999995e-06], + ['Fe58',8.560391999999999e-07], + ['C0',0.0011922], + ['H1',0.000275007163713], + ['H2',4.2836286999999996e-08], + ['N14',2.9579252856e-05], + ['N15',1.0874714400000001e-07], + ['O16',4.3994319831e-05], + ['O17',1.6680169000000002e-08]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.042431], + ['Pu240',0.0043997], + ['Fe54',1.665825e-05], + ['Fe56',0.0002614989], + ['Fe57',6.03915e-06], + ['Fe58',8.036999999999999e-07], + ['C0',0.0013956], + ['H1',0.0004330125521208], + ['H2',6.74478792e-08], + ['N14',4.6574769402e-05], + ['N15',1.71230598e-07], + ['O16',6.9270736437e-05], + ['O17',2.6263563000000002e-08]]) +# Material Name: Steel reflector +m5 = mcdc.material(nuclides=[ + ['Fe54',0.0046715578], + ['Fe56',0.07333346696], + ['Fe57',0.0016935895599999998], + ['Fe58',0.00022538567999999998], + ['C0',0.0011341], + ['Si28',0.000149107723656], + ['Si29',7.5712647719999995e-06], + ['Si30',4.991011571999999e-06], + ['Cr50',1.1383031e-05], + ['Cr52',0.0002195104222], + ['Cr53',2.48907198e-05], + ['Cr54',6.195827e-06], + ['Mn55',0.00033061], + ['Ni58',0.00015800648489999999], + ['Ni60',6.086381509999999e-05], + ['Ni61',2.6457078999999998e-06], + ['Ni62',8.435674500000001e-06], + ['Ni64',2.1483176e-06], + ['Cu63',0.000148236855], + ['Cu65',6.6133145e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.7, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-032/mcdc/pu-met-fast-032_case-2.py b/icsbep/openmc/pu-met-fast-032/mcdc/pu-met-fast-032_case-2.py new file mode 100644 index 0000000..8966b4a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/mcdc/pu-met-fast-032_case-2.py @@ -0,0 +1,78 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.042126], + ['Pu240',0.0045761], + ['Fe54',1.67278055e-05], + ['Fe56',0.0002625907726], + ['Fe57',6.064366100000001e-06], + ['Fe58',8.070558000000001e-07], + ['C0',0.00126], + ['H1',0.00032394954024], + ['H2',5.045976e-08], + ['N14',3.4843897564000004e-05], + ['N15',1.28102436e-07], + ['O16',5.1823351502999994e-05], + ['O17',1.9648496999999998e-08]]) +# Material Name: Steel reflector +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0046715578], + ['Fe56',0.07333346696], + ['Fe57',0.0016935895599999998], + ['Fe58',0.00022538567999999998], + ['C0',0.0011341], + ['Si28',0.000149107723656], + ['Si29',7.5712647719999995e-06], + ['Si30',4.991011571999999e-06], + ['Cr50',1.1383031e-05], + ['Cr52',0.0002195104222], + ['Cr53',2.48907198e-05], + ['Cr54',6.195827e-06], + ['Mn55',0.00033061], + ['Ni58',0.00015800648489999999], + ['Ni60',6.086381509999999e-05], + ['Ni61',2.6457078999999998e-06], + ['Ni62',8.435674500000001e-06], + ['Ni64',2.1483176e-06], + ['Cu63',0.000148236855], + ['Cu65',6.6133145e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.7, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-032/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..bc91477 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-1/generate_materials.py @@ -0,0 +1,69 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.1607e-02) +mat.add_nuclide('Pu240', 4.8551e-03) +mat.add_nuclide('Pu241', 9.0948e-04) +mat.add_element('Fe', 3.0510e-04) +mat.add_element('C', 1.9920e-03) +mat.add_element('H', 8.3342e-04) +mat.add_element('N', 8.9958e-05) +mat.add_element('O', 1.3336e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.2276e-02) +mat.add_nuclide('Pu240', 4.6060e-03) +mat.add_nuclide('Pu241', 6.7147e-04) +mat.add_element('Fe', 2.6534e-04) +mat.add_element('C', 1.1053e-03) +mat.add_element('H', 2.0011e-04) +mat.add_element('N', 2.1600e-05) +mat.add_element('O', 3.2020e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.1681e-02) +mat.add_nuclide('Pu240', 4.7176e-03) +mat.add_nuclide('Pu241', 7.4079e-04) +mat.add_element('Fe', 3.0356e-04) +mat.add_element('C', 1.1922e-03) +mat.add_element('H', 2.7505e-04) +mat.add_element('N', 2.9688e-05) +mat.add_element('O', 4.4011e-05) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.2431e-02) +mat.add_nuclide('Pu240', 4.3997e-03) +mat.add_nuclide('Pu241', 5.9425e-04) +mat.add_element('Fe', 2.8500e-04) +mat.add_element('C', 1.3956e-03) +mat.add_element('H', 4.3308e-04) +mat.add_element('N', 4.6746e-05) +mat.add_element('O', 6.9297e-05) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Steel reflector" +mat.set_density('sum') +mat.add_element('Fe', 7.9924e-02) +mat.add_element('C', 1.1341e-03) +mat.add_element('Si', 1.6167e-04) +mat.add_element('Cr', 2.6198e-04) +mat.add_element('Mn', 3.3061e-04) +mat.add_element('Ni', 2.3210e-04) +mat.add_element('Cu', 2.1437e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-032/openmc/case-1/geometry.xml new file mode 100644 index 0000000..2d60b61 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-1/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-032/openmc/case-1/materials.xml new file mode 100644 index 0000000..7a1f892 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-1/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-032/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-032/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..441f0a1 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-2/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.2126e-02) +mat.add_nuclide('Pu240', 4.5761e-03) +mat.add_nuclide('Pu241', 6.7271e-04) +mat.add_element('Fe', 2.8619e-04) +mat.add_element('C', 1.2600e-03) +mat.add_element('H', 3.2400e-04) +mat.add_element('N', 3.4972e-05) +mat.add_element('O', 5.1843e-05) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Steel reflector" +mat.set_density('sum') +mat.add_element('Fe', 7.9924e-02) +mat.add_element('C', 1.1341e-03) +mat.add_element('Si', 1.6167e-04) +mat.add_element('Cr', 2.6198e-04) +mat.add_element('Mn', 3.3061e-04) +mat.add_element('Ni', 2.3210e-04) +mat.add_element('Cu', 2.1437e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-032/openmc/case-2/geometry.xml new file mode 100644 index 0000000..c14fee3 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-032/openmc/case-2/materials.xml new file mode 100644 index 0000000..ea5a7d3 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-2/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-032/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-032/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-032/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-035/mcdc/pu-met-fast-035.py b/icsbep/openmc/pu-met-fast-035/mcdc/pu-met-fast-035.py new file mode 100644 index 0000000..ba0e207 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-035/mcdc/pu-met-fast-035.py @@ -0,0 +1,124 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.03685], + ['Pu240',0.0006736499999999999], + ['Ga69',0.0013940848439999995], + ['Ga71',0.0009252151559999999], + ['C0',0.00030426], + ['Ni58',0.00113688423], + ['Ni60',0.00043792577], + ['Ni61',1.9036329999999998e-05], + ['Ni62',6.069615000000001e-05], + ['Ni64',1.545752e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.00139180074], + ['Ga71',0.00092369926], + ['C0',0.00030205], + ['Ni58',0.0013159264769999999], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.0013811616239999998], + ['Ga71',0.000916638376], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.1340633599999997e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.001399674888], + ['Ga71',0.000928925112], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999993e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036471], + ['Pu240',0.0006666499999999999], + ['Ga69',0.0013718448839999998], + ['Ga71',0.0009104551160000001], + ['C0',0.0003011], + ['Ni58',0.0013421360835], + ['Ni60',0.0005169884165], + ['Ni61',2.24731285e-05], + ['Ni62',7.165416750000001e-05], + ['Ni64',1.8248204000000004e-05]]) +# Material Name: Lead reflector +m6 = mcdc.material(nuclides=[ + ['Pb204',0.00045841600000000006], + ['Pb206',0.007891304], + ['Pb207',0.007236424000000001], + ['Pb208',0.017157856000000003], + ['Fe54',1.07238215e-06], + ['Fe56',1.683410638e-05], + ['Fe57',3.8877293e-07], + ['Fe58',5.1738539999999997e-08]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.2, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-035/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-035/openmc/generate_materials.py new file mode 100644 index 0000000..5b53afd --- /dev/null +++ b/icsbep/openmc/pu-met-fast-035/openmc/generate_materials.py @@ -0,0 +1,62 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6850e-02) +mat.add_nuclide('Pu240', 6.7365e-04) +mat.add_element('Ga', 2.3193e-03) +mat.add_element('C', 3.0426e-04) +mat.add_element('Ni', 1.6700e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.3155e-03) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.2978e-03) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.3286e-03) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6471e-02) +mat.add_nuclide('Pu240', 6.6665e-04) +mat.add_element('Ga', 2.2823e-03) +mat.add_element('C', 3.0110e-04) +mat.add_element('Ni', 1.9715e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Lead reflector" +mat.set_density('sum') +mat.add_element('Pb', 3.2744e-02) +mat.add_element('Fe', 1.8347e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-035/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-035/openmc/geometry.xml new file mode 100644 index 0000000..4c101d7 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-035/openmc/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-035/openmc/materials.xml b/icsbep/openmc/pu-met-fast-035/openmc/materials.xml new file mode 100644 index 0000000..6dfe47e --- /dev/null +++ b/icsbep/openmc/pu-met-fast-035/openmc/materials.xml @@ -0,0 +1,79 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-035/openmc/settings.xml b/icsbep/openmc/pu-met-fast-035/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-035/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-036/mcdc/pu-met-fast-036.py b/icsbep/openmc/pu-met-fast-036/mcdc/pu-met-fast-036.py new file mode 100644 index 0000000..dd3969b --- /dev/null +++ b/icsbep/openmc/pu-met-fast-036/mcdc/pu-met-fast-036.py @@ -0,0 +1,163 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.035932], + ['Pu240',0.00065685], + ['Ga69',0.00135934242], + ['Ga71',0.00090215758], + ['C0',0.00029667], + ['Ni58',0.0028752278714999995], + ['Ni60',0.0011075326285], + ['Ni61',4.814367649999999e-05], + ['Ni62',0.00015350310750000001], + ['Ni64',3.9092716e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036826], + ['Pu240',0.0006732000000000001], + ['Ga69',0.0013931832239999999], + ['Ga71',0.000924616776], + ['C0',0.00030406], + ['Ni58',0.0010703050217999999], + ['Ni60',0.00041227957819999996], + ['Ni61',1.79215078e-05], + ['Ni62',5.7141609e-05], + ['Ni64',1.4552283199999998e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.00139180074], + ['Ga71',0.00092369926], + ['C0',0.00030205], + ['Ni58',0.0013159264769999999], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.0013811616239999998], + ['Ga71',0.000916638376], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.1340633599999997e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.001399674888], + ['Ga71',0.000928925112], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999993e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Layer 6 +# Depletable +m6 = mcdc.material(nuclides=[ + ['Pu239',0.036471], + ['Pu240',0.0006666499999999999], + ['Ga69',0.0013718448839999998], + ['Ga71',0.0009104551160000001], + ['C0',0.0003011], + ['Ni58',0.0013421360835], + ['Ni60',0.0005169884165], + ['Ni61',2.24731285e-05], + ['Ni62',7.165416750000001e-05], + ['Ni64',1.8248204000000004e-05]]) +# Material Name: Cadmium reflector +m7 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +# Material Name: Polyethlyene reflector, layer 1 +# S(a,b): c_H_in_CH2 (Not Implemented) +m8 = mcdc.material(nuclides=[ + ['H1',0.07383349937969999], + ['H2',1.15006203e-05], + ['C0',0.036922]]) +# Material Name: Polyethlyene reflector, layer 2 +# S(a,b): c_H_in_CH2 (Not Implemented) +m9 = mcdc.material(nuclides=[ + ['H1',0.07898469700722], + ['H2',1.2302992779999999e-05], + ['C0',0.039498]]) +# Material Name: Polyethlyene reflector, layer 3 +# S(a,b): c_H_in_CH2 (Not Implemented) +m10 = mcdc.material(nuclides=[ + ['H1',0.07898369716296], + ['H2',1.2302837039999999e-05], + ['C0',0.039498]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.16, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.4, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.05, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.75, bc='interface') +s10 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.55, bc='interface') +s11 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +c9 = mcdc.cell(+s8 & -s9, fill=m8) +c10 = mcdc.cell(+s9 & -s10, fill=m9) +c11 = mcdc.cell(+s10 & -s11, fill=m10) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-036/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-036/openmc/generate_materials.py new file mode 100644 index 0000000..53420e0 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-036/openmc/generate_materials.py @@ -0,0 +1,95 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.5932e-02) +mat.add_nuclide('Pu240', 6.5685e-04) +mat.add_element('Ga', 2.2615e-03) +mat.add_element('C', 2.9667e-04) +mat.add_element('Ni', 4.2235e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6826e-02) +mat.add_nuclide('Pu240', 6.7320e-04) +mat.add_element('Ga', 2.3178e-03) +mat.add_element('C', 3.0406e-04) +mat.add_element('Ni', 1.5722e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.3155e-03) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.2978e-03) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.3286e-03) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Layer 6" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6471e-02) +mat.add_nuclide('Pu240', 6.6665e-04) +mat.add_element('Ga', 2.2823e-03) +mat.add_element('C', 3.0110e-04) +mat.add_element('Ni', 1.9715e-03) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Cadmium reflector" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Polyethlyene reflector, layer 1" +mat.set_density('sum') +mat.add_element('H', 7.3845e-02) +mat.add_element('C', 3.6922e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(9) +mat.name = "Polyethlyene reflector, layer 2" +mat.set_density('sum') +mat.add_element('H', 7.8997e-02) +mat.add_element('C', 3.9498e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(10) +mat.name = "Polyethlyene reflector, layer 3" +mat.set_density('sum') +mat.add_element('H', 7.8996e-02) +mat.add_element('C', 3.9498e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-036/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-036/openmc/geometry.xml new file mode 100644 index 0000000..5786255 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-036/openmc/geometry.xml @@ -0,0 +1,35 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-036/openmc/materials.xml b/icsbep/openmc/pu-met-fast-036/openmc/materials.xml new file mode 100644 index 0000000..fce4b91 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-036/openmc/materials.xml @@ -0,0 +1,113 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-036/openmc/settings.xml b/icsbep/openmc/pu-met-fast-036/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-036/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-039/mcdc/pu-met-fast-039.py b/icsbep/openmc/pu-met-fast-039/mcdc/pu-met-fast-039.py new file mode 100644 index 0000000..ced2501 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-039/mcdc/pu-met-fast-039.py @@ -0,0 +1,145 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036581], + ['Pu240',0.0006687999999999999], + ['Ga69',0.0013916204159999997], + ['Ga71',0.0009235795839999999], + ['C0',0.00030207], + ['Ni58',0.0013078934028], + ['Ni60',0.0005037981972], + ['Ni61',2.1899758799999998e-05], + ['Ni62',6.9826014e-05], + ['Ni64',1.7782627200000002e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.0013811616239999998], + ['Ga71',0.000916638376], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.1340633599999997e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.001399674888], + ['Ga71',0.000928925112], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999993e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036471], + ['Pu240',0.0006666499999999999], + ['Ga69',0.0013718448839999998], + ['Ga71',0.0009104551160000001], + ['C0',0.0003011], + ['Ni58',0.0013421360835], + ['Ni60',0.0005169884165], + ['Ni61',2.24731285e-05], + ['Ni62',7.165416750000001e-05], + ['Ni64',1.8248204000000004e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036707], + ['Pu240',0.0006711], + ['Ga69',0.001396669488], + ['Ga71',0.000926930512], + ['C0',0.00030311], + ['Ni58',0.0011221115426999998], + ['Ni60',0.00043223535729999997], + ['Ni61',1.8788971699999998e-05], + ['Ni62',5.99074635e-05], + ['Ni64',1.52566648e-05]]) +# Material Name: Duralumin reflector, layer 1 +m6 = mcdc.material(nuclides=[ + ['Al27',0.055645], + ['Fe54',5.951963500000001e-05], + ['Fe56',0.000934330982], + ['Fe57',2.1577777e-05], + ['Fe58',2.871606e-06], + ['Cu63',0.0007249686], + ['Cu65',0.0003234314]]) +# Material Name: Duralumin reflector, layer 2 +m7 = mcdc.material(nuclides=[ + ['Al27',0.053497], + ['Fe54',5.7223719000000004e-05], + ['Fe56',0.0008982900107999999], + ['Fe57',2.07454338e-05], + ['Fe58',2.7608364e-06], + ['Cu63',0.0006969628499999999], + ['Cu65',0.00031093715]]) +# Material Name: Duralumin reflector, layer 3 +m8 = mcdc.material(nuclides=[ + ['Al27',0.051557], + ['Fe54',5.5149328500000005e-05], + ['Fe56',0.0008657265162000001], + ['Fe57',1.9993400700000002e-05], + ['Fe58',2.6607546e-06], + ['Cu63',0.00067169544], + ['Cu65',0.00029966456]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.112, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.75, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.35, bc='interface') +s8 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.15, bc='interface') +s9 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=11.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +c8 = mcdc.cell(+s7 & -s8, fill=m7) +c9 = mcdc.cell(+s8 & -s9, fill=m8) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-039/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-039/openmc/generate_materials.py new file mode 100644 index 0000000..3a235e2 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-039/openmc/generate_materials.py @@ -0,0 +1,79 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6581e-02) +mat.add_nuclide('Pu240', 6.6880e-04) +mat.add_element('Ga', 2.3152e-03) +mat.add_element('C', 3.0207e-04) +mat.add_element('Ni', 1.9212e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.2978e-03) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.3286e-03) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6471e-02) +mat.add_nuclide('Pu240', 6.6665e-04) +mat.add_element('Ga', 2.2823e-03) +mat.add_element('C', 3.0110e-04) +mat.add_element('Ni', 1.9715e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6707e-02) +mat.add_nuclide('Pu240', 6.7110e-04) +mat.add_element('Ga', 2.3236e-03) +mat.add_element('C', 3.0311e-04) +mat.add_element('Ni', 1.6483e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Duralumin reflector, layer 1" +mat.set_density('sum') +mat.add_element('Al', 5.5645e-02) +mat.add_element('Fe', 1.0183e-03) +mat.add_element('Cu', 1.0484e-03) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Duralumin reflector, layer 2" +mat.set_density('sum') +mat.add_element('Al', 5.3497e-02) +mat.add_element('Fe', 9.7902e-04) +mat.add_element('Cu', 1.0079e-03) +mats.append(mat) + +mat = openmc.Material(8) +mat.name = "Duralumin reflector, layer 3" +mat.set_density('sum') +mat.add_element('Al', 5.1557e-02) +mat.add_element('Fe', 9.4353e-04) +mat.add_element('Cu', 9.7136e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-039/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-039/openmc/geometry.xml new file mode 100644 index 0000000..02ff4f2 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-039/openmc/geometry.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-039/openmc/materials.xml b/icsbep/openmc/pu-met-fast-039/openmc/materials.xml new file mode 100644 index 0000000..3be9ff6 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-039/openmc/materials.xml @@ -0,0 +1,98 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-039/openmc/settings.xml b/icsbep/openmc/pu-met-fast-039/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-039/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-040/mcdc/pu-met-fast-040.py b/icsbep/openmc/pu-met-fast-040/mcdc/pu-met-fast-040.py new file mode 100644 index 0000000..f3be894 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-040/mcdc/pu-met-fast-040.py @@ -0,0 +1,122 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Layer 1 +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.036849], + ['Pu240',0.00067362], + ['Ga69',0.0013940848439999997], + ['Ga71',0.0009252151559999999], + ['C0',0.00030425], + ['Ni58',0.0010148904252], + ['Ni60',0.0003909339748], + ['Ni61',1.69936292e-05], + ['Ni62',5.4183126000000004e-05], + ['Ni64',1.3798844799999999e-05]]) +# Material Name: Layer 2 +# Depletable +m2 = mcdc.material(nuclides=[ + ['Pu239',0.036579], + ['Pu240',0.00066875], + ['Ga69',0.00139180074], + ['Ga71',0.00092369926], + ['C0',0.00030205], + ['Ni58',0.0013159264769999999], + ['Ni60',0.000506892523], + ['Ni61',2.2034267e-05], + ['Ni62',7.025488500000001e-05], + ['Ni64',1.7891848000000002e-05]]) +# Material Name: Layer 3 +# Depletable +m3 = mcdc.material(nuclides=[ + ['Pu239',0.036512], + ['Pu240',0.00066739], + ['Ga69',0.0013811616239999998], + ['Ga71',0.000916638376], + ['C0',0.00022608], + ['Ni58',0.0015695810064], + ['Ni60',0.0006045997936], + ['Ni61',2.62815344e-05], + ['Ni62',8.3797032e-05], + ['Ni64',2.1340633599999997e-05]]) +# Material Name: Layer 4 +# Depletable +m4 = mcdc.material(nuclides=[ + ['Pu239',0.036576], + ['Pu240',0.00066878], + ['Ga69',0.001399674888], + ['Ga71',0.000928925112], + ['C0',0.00030206], + ['Ni58',0.0012683407238999998], + ['Ni60',0.0004885625761], + ['Ni61',2.1237476899999993e-05], + ['Ni62',6.77143695e-05], + ['Ni64',1.72448536e-05]]) +# Material Name: Layer 5 +# Depletable +m5 = mcdc.material(nuclides=[ + ['Pu239',0.036471], + ['Pu240',0.0006666499999999999], + ['Ga69',0.0013718448839999998], + ['Ga71',0.0009104551160000001], + ['C0',0.0003011], + ['Ni58',0.0013421360835], + ['Ni60',0.0005169884165], + ['Ni61',2.24731285e-05], + ['Ni62',7.165416750000001e-05], + ['Ni64',1.8248204000000004e-05]]) +# Material Name: Copper reflector +m6 = mcdc.material(nuclides=[ + ['Cu63',0.058202172], + ['Cu65',0.025965828], + ['Fe54',2.9519588000000003e-07], + ['Fe56',4.633944016e-06], + ['Fe57',1.07017976e-07], + ['Fe58',1.4242128e-08]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=1.531, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=3.15, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.02, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.66, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.35, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.0, bc='interface') +s7 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.6, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=mvoid) +c2 = mcdc.cell(+s1 & -s2, fill=m1) +c3 = mcdc.cell(+s2 & -s3, fill=m2) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +c7 = mcdc.cell(+s6 & -s7, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-040/openmc/generate_materials.py b/icsbep/openmc/pu-met-fast-040/openmc/generate_materials.py new file mode 100644 index 0000000..451c593 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-040/openmc/generate_materials.py @@ -0,0 +1,62 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Layer 1" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6849e-02) +mat.add_nuclide('Pu240', 6.7362e-04) +mat.add_element('Ga', 2.3193e-03) +mat.add_element('C', 3.0425e-04) +mat.add_element('Ni', 1.4908e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Layer 2" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6579e-02) +mat.add_nuclide('Pu240', 6.6875e-04) +mat.add_element('Ga', 2.3155e-03) +mat.add_element('C', 3.0205e-04) +mat.add_element('Ni', 1.9330e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Layer 3" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6512e-02) +mat.add_nuclide('Pu240', 6.6739e-04) +mat.add_element('Ga', 2.2978e-03) +mat.add_element('C', 2.2608e-04) +mat.add_element('Ni', 2.3056e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Layer 4" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6576e-02) +mat.add_nuclide('Pu240', 6.6878e-04) +mat.add_element('Ga', 2.3286e-03) +mat.add_element('C', 3.0206e-04) +mat.add_element('Ni', 1.8631e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Layer 5" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.6471e-02) +mat.add_nuclide('Pu240', 6.6665e-04) +mat.add_element('Ga', 2.2823e-03) +mat.add_element('C', 3.0110e-04) +mat.add_element('Ni', 1.9715e-03) +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Copper reflector" +mat.set_density('sum') +mat.add_element('Cu', 8.4168e-02) +mat.add_element('Fe', 5.0504e-06) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-040/openmc/geometry.xml b/icsbep/openmc/pu-met-fast-040/openmc/geometry.xml new file mode 100644 index 0000000..b9c556c --- /dev/null +++ b/icsbep/openmc/pu-met-fast-040/openmc/geometry.xml @@ -0,0 +1,27 @@ + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-040/openmc/materials.xml b/icsbep/openmc/pu-met-fast-040/openmc/materials.xml new file mode 100644 index 0000000..2250915 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-040/openmc/materials.xml @@ -0,0 +1,77 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-040/openmc/settings.xml b/icsbep/openmc/pu-met-fast-040/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-040/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-1.py b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-1.py new file mode 100644 index 0000000..3658128 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-1.py @@ -0,0 +1,83 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium-Gallium alloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037028], + ['Pu240',0.0019931], + ['Pu240',0.00013594], + ['Ga69',0.00077419104], + ['Ga71',0.00051380896]]) +# Material Name: Nickel coating +m2 = mcdc.material(nuclides=[ + ['Ni58',0.08824127778], + ['Ni60',0.033990382220000004], + ['Ni61',0.00147753838], + ['Ni62',0.004711038900000001], + ['Ni64',0.0011997627200000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.9786725421e-05], + ['N15',1.4627457899999999e-07], + ['O16',8.7365875779e-06], + ['O17',3.3124221000000003e-09]]) +# Material Name: Tamper +m4 = mcdc.material(nuclides=[ + ['Mo100',0.0061191345599999995], + ['Mo92',0.00919942551], + ['Mo94',0.005769344129999999], + ['Mo95',0.00996808527], + ['Mo96',0.010470477269999999], + ['Mo97',0.006017400179999999], + ['Mo98',0.015255133079999999]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['C0',0.03967], + ['H1',0.0793276435884], + ['H2',1.2356411599999999e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.295, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.308, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.335, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.335, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.342, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.8975, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m3) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-2.py b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-2.py new file mode 100644 index 0000000..124ec84 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-2.py @@ -0,0 +1,80 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium-Gallium alloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037028], + ['Pu240',0.0019931], + ['Pu240',0.00013594], + ['Ga69',0.00077419104], + ['Ga71',0.00051380896]]) +# Material Name: Nickel coating +m2 = mcdc.material(nuclides=[ + ['Ni58',0.08824127778], + ['Ni60',0.033990382220000004], + ['Ni61',0.00147753838], + ['Ni62',0.004711038900000001], + ['Ni64',0.0011997627200000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.9786725421e-05], + ['N15',1.4627457899999999e-07], + ['O16',8.7365875779e-06], + ['O17',3.3124221000000003e-09]]) +# Material Name: Tamper +m4 = mcdc.material(nuclides=[ + ['Fe54',0.0050169973], + ['Fe56',0.07875612836], + ['Fe57',0.00181882246], + ['Fe58',0.00024205187999999997]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['C0',0.041216], + ['H1',0.08241816219606], + ['H2',1.283780394e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.295, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.308, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.335, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.335, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.342, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.8412, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m3) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-3.py b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-3.py new file mode 100644 index 0000000..8643cfd --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-3.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium-Gallium alloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037028], + ['Pu240',0.0019931], + ['Pu240',0.00013594], + ['Ga69',0.00077419104], + ['Ga71',0.00051380896]]) +# Material Name: Nickel coating +m2 = mcdc.material(nuclides=[ + ['Ni58',0.08824127778], + ['Ni60',0.033990382220000004], + ['Ni61',0.00147753838], + ['Ni62',0.004711038900000001], + ['Ni64',0.0011997627200000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.9786725421e-05], + ['N15',1.4627457899999999e-07], + ['O16',8.7365875779e-06], + ['O17',3.3124221000000003e-09]]) +# Material Name: Tamper +m4 = mcdc.material(nuclides=[ + ['Be9',0.12199]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['C0',0.039756], + ['H1',0.07949961680112], + ['H2',1.238319888e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.295, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.308, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.335, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.335, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.342, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.3404, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m3) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-4.py b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-4.py new file mode 100644 index 0000000..f569613 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-4.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium-Gallium alloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037028], + ['Pu240',0.0019931], + ['Pu240',0.00013594], + ['Ga69',0.00077419104], + ['Ga71',0.00051380896]]) +# Material Name: Nickel coating +m2 = mcdc.material(nuclides=[ + ['Ni58',0.08824127778], + ['Ni60',0.033990382220000004], + ['Ni61',0.00147753838], + ['Ni62',0.004711038900000001], + ['Ni64',0.0011997627200000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.9786725421e-05], + ['N15',1.4627457899999999e-07], + ['O16',8.7365875779e-06], + ['O17',3.3124221000000003e-09]]) +# Material Name: Tamper +m4 = mcdc.material(nuclides=[ + ['Al27',0.059324]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['C0',0.040228], + ['H1',0.08044346978256], + ['H2',1.253021744e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.295, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.308, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.335, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.335, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.342, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.6328, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m3) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-5.py b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-5.py new file mode 100644 index 0000000..4f920a2 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/mcdc/pu-met-fast-044_case-5.py @@ -0,0 +1,77 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium-Gallium alloy +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.037028], + ['Pu240',0.0019931], + ['Pu240',0.00013594], + ['Ga69',0.00077419104], + ['Ga71',0.00051380896]]) +# Material Name: Nickel coating +m2 = mcdc.material(nuclides=[ + ['Ni58',0.08824127778], + ['Ni60',0.033990382220000004], + ['Ni61',0.00147753838], + ['Ni62',0.004711038900000001], + ['Ni64',0.0011997627200000002]]) +# Material Name: Air +m3 = mcdc.material(nuclides=[ + ['N14',3.9786725421e-05], + ['N15',1.4627457899999999e-07], + ['O16',8.7365875779e-06], + ['O17',3.3124221000000003e-09]]) +# Material Name: Tamper +m4 = mcdc.material(nuclides=[ + ['C0',0.086272]]) +# Material Name: Polyethylene +# S(a,b): c_H_in_CH2 (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['C0',0.039756], + ['H1',0.07949961680112], + ['H2',1.238319888e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.295, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.308, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.335, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.335, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.342, bc='interface') +s6 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.1274, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +c4 = mcdc.cell(+s3 & -s4, fill=m4) +c5 = mcdc.cell(+s4 & -s5, fill=m3) +c6 = mcdc.cell(+s5 & -s6, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-met-fast-044/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..4b223e2 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-1/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium-Gallium alloy" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7028e-02) +mat.add_nuclide('Pu240', 1.9931e-03) +mat.add_nuclide('Pu240', 1.3594e-04) +mat.add_element('Ga', 1.2880e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel coating" +mat.set_density('sum') +mat.add_element('Ni', 1.2962e-01) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.9933e-05) +mat.add_element('O', 8.7399e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Tamper" +mat.set_density('sum') +mat.add_element('Mo', 6.2799e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9670e-02) +mat.add_element('H', 7.9340e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-1/geometry.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-1/geometry.xml new file mode 100644 index 0000000..cbe5ae4 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-1/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-1/materials.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-1/materials.xml new file mode 100644 index 0000000..7d3b4bb --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-1/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-1/settings.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-met-fast-044/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..7d54355 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-2/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium-Gallium alloy" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7028e-02) +mat.add_nuclide('Pu240', 1.9931e-03) +mat.add_nuclide('Pu240', 1.3594e-04) +mat.add_element('Ga', 1.2880e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel coating" +mat.set_density('sum') +mat.add_element('Ni', 1.2962e-01) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.9933e-05) +mat.add_element('O', 8.7399e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Tamper" +mat.set_density('sum') +mat.add_element('Fe', 8.5834e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 4.1216e-02) +mat.add_element('H', 8.2431e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-2/geometry.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-2/geometry.xml new file mode 100644 index 0000000..50326c0 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-2/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-2/materials.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-2/materials.xml new file mode 100644 index 0000000..e3c9565 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-2/materials.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-2/settings.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-met-fast-044/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..0502b4a --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-3/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium-Gallium alloy" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7028e-02) +mat.add_nuclide('Pu240', 1.9931e-03) +mat.add_nuclide('Pu240', 1.3594e-04) +mat.add_element('Ga', 1.2880e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel coating" +mat.set_density('sum') +mat.add_element('Ni', 1.2962e-01) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.9933e-05) +mat.add_element('O', 8.7399e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Tamper" +mat.set_density('sum') +mat.add_element('Be', 1.2199e-01) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9756e-02) +mat.add_element('H', 7.9512e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-3/geometry.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-3/geometry.xml new file mode 100644 index 0000000..97f7dfd --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-3/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-3/materials.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-3/materials.xml new file mode 100644 index 0000000..49d0919 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-3/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-3/settings.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-met-fast-044/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..69809a2 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-4/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium-Gallium alloy" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7028e-02) +mat.add_nuclide('Pu240', 1.9931e-03) +mat.add_nuclide('Pu240', 1.3594e-04) +mat.add_element('Ga', 1.2880e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel coating" +mat.set_density('sum') +mat.add_element('Ni', 1.2962e-01) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.9933e-05) +mat.add_element('O', 8.7399e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Tamper" +mat.set_density('sum') +mat.add_element('Al', 5.9324e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 4.0228e-02) +mat.add_element('H', 8.0456e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-4/geometry.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-4/geometry.xml new file mode 100644 index 0000000..07b1afe --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-4/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-4/materials.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-4/materials.xml new file mode 100644 index 0000000..a88dd85 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-4/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-4/settings.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-met-fast-044/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..9da8a03 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-5/generate_materials.py @@ -0,0 +1,41 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium-Gallium alloy" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.7028e-02) +mat.add_nuclide('Pu240', 1.9931e-03) +mat.add_nuclide('Pu240', 1.3594e-04) +mat.add_element('Ga', 1.2880e-03) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Nickel coating" +mat.set_density('sum') +mat.add_element('Ni', 1.2962e-01) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Air" +mat.set_density('sum') +mat.add_element('N', 3.9933e-05) +mat.add_element('O', 8.7399e-06) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Tamper" +mat.set_density('sum') +mat.add_element('C', 8.6272e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Polyethylene" +mat.set_density('sum') +mat.add_element('C', 3.9756e-02) +mat.add_element('H', 7.9512e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-5/geometry.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-5/geometry.xml new file mode 100644 index 0000000..c679b95 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-5/geometry.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-5/materials.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-5/materials.xml new file mode 100644 index 0000000..fe4e929 --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-5/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-fast-044/openmc/case-5/settings.xml b/icsbep/openmc/pu-met-fast-044/openmc/case-5/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-met-fast-044/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-inter-002/mcdc/pu-met-inter-002.py b/icsbep/openmc/pu-met-inter-002/mcdc/pu-met-inter-002.py new file mode 100644 index 0000000..ca1bcfb --- /dev/null +++ b/icsbep/openmc/pu-met-inter-002/mcdc/pu-met-inter-002.py @@ -0,0 +1,209 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Core region +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.6938e-09], + ['Pu239',0.00106299], + ['Pu240',5.03037e-05], + ['Pu242',1.15592e-07], + ['Am241',2.98613e-06], + ['Cr50',0.0004276344655], + ['Cr52',0.0082465050011], + ['Cr53',0.0009350874699], + ['Cr54',0.00023276306350000005], + ['Al27',0.000111659], + ['Mn55',0.000805254], + ['Co59',3.71924e-06], + ['Ni58',0.00278113198032], + ['Ni60',0.00107128705968], + ['Ni61',4.6568106719999996e-05], + ['Ni62',0.0001484795016], + ['Ni64',3.781335168e-05], + ['C0',0.0258213], + ['Cu63',7.00012365e-05], + ['Cu65',3.12297635e-05], + ['Fe54',0.002060987915], + ['Fe56',0.032353102678], + ['Fe57',0.000747174233], + ['Fe58',9.9435174e-05], + ['Mo100',7.237765248e-06], + ['Mo92',1.0881160008000002e-05], + ['Mo94',6.824030103999999e-06], + ['Mo95',1.1790337416000002e-05], + ['Mo96',1.2384571015999997e-05], + ['Mo97',7.117432944000001e-06], + ['Mo98',1.8043903264e-05], + ['Si28',0.0002578529724536], + ['Si29',1.3093038233199999e-05], + ['Si30',8.6309893132e-06]]) +# Material Name: Axial stainless steel +m2 = mcdc.material(nuclides=[ + ['Cr50',0.0006833685650000001], + ['Cr52',0.013178082553], + ['Cr53',0.001494288777], + ['Cr54',0.000371960105], + ['Mn55',0.00156081], + ['Co59',3.7358199999999996e-06], + ['Ni58',0.00472900951233], + ['Ni60',0.0018216059976699998], + ['Ni61',7.918395143e-05], + ['Ni62',0.00025247308665], + ['Ni64',6.429745192e-05], + ['C0',0.000235948], + ['Cu63',2.0614652250000002e-05], + ['Cu65',9.19684775e-06], + ['Fe54',0.0032452667450000006], + ['Fe56',0.050943747633999996], + ['Fe57',0.001176513299], + ['Fe58',0.000156572322], + ['Mo100',1.48225728e-06], + ['Mo92',2.22840588e-06], + ['Mo94',1.3975264400000002e-06], + ['Mo95',2.41460076e-06], + ['Mo96',2.53629676e-06], + ['Mo97',1.45761384e-06], + ['Mo98',3.69529904e-06], + ['Si28',0.000872022401432], + ['Si29',4.4278809484e-05], + ['Si30',2.9188789084e-05]]) +# Material Name: Radial stainless steel +m3 = mcdc.material(nuclides=[ + ['Cr50',0.0006790626700000001], + ['Cr52',0.013095047654], + ['Cr53',0.001484873286], + ['Cr54',0.0003696163899999999], + ['Mn55',0.00142057], + ['Co59',3.77932e-06], + ['Ni58',0.0046184049729], + ['Ni60',0.0017790013271], + ['Ni61',7.73319559e-05], + ['Ni62',0.00024656811450000005], + ['Ni64',6.27936296e-05], + ['C0',0.00023710599999999998], + ['Cu63',3.4855195800000004e-05], + ['Cu65',1.55500042e-05], + ['Fe54',0.0032262295800000004], + ['Fe56',0.050644904856], + ['Fe57',0.001169611716], + ['Fe58',0.000155653848], + ['Mo100',4.521440112e-06], + ['Mo92',6.7974729269999994e-06], + ['Mo94',4.262979301e-06], + ['Mo95',7.365437079000001e-06], + ['Mo96',7.736655479e-06], + ['Mo97',4.446268386e-06], + ['Mo98',1.1272046716e-05], + ['Si28',0.000796274165248], + ['Si29',4.0432530176e-05], + ['Si30',2.6653304576e-05]]) +# Material Name: Iron radial reflector +m4 = mcdc.material(nuclides=[ + ['Cr50',7.9408351e-05], + ['Cr52',0.0015313110062000002], + ['Cr53',0.00017363837579999997], + ['Cr54',4.3222267e-05], + ['Mn55',0.00055035], + ['Co59',3.77222e-06], + ['Ni58',0.0005183613435149999], + ['Ni60',0.000199671861485], + ['Ni61',8.679597565e-06], + ['Ni62',2.7674355075000005e-05], + ['Ni64',7.047842359999999e-06], + ['C0',0.00042731499999999994], + ['Cu63',2.0085101550000002e-05], + ['Cu65',8.96059845e-06], + ['Fe54',0.00448037954], + ['Fe56',0.070332377128], + ['Fe57',0.0016242813080000003], + ['Fe58',0.000216162024], + ['Mo100',1.42491384e-06], + ['Mo92',2.142196515e-06], + ['Mo94',1.343460945e-06], + ['Mo95',2.3211881550000002e-06], + ['Mo96',2.438176155e-06], + ['Mo97',1.40122377e-06], + ['Mo98',3.55234062e-06], + ['Si28',0.0001338695359264], + ['Si29',6.7975130768e-06], + ['Si30',4.4809509968e-06]]) +# Material Name: Empty matrix +m5 = mcdc.material(nuclides=[ + ['Cr50',5.1586881500000005e-05], + ['Cr52',0.0009948016603], + ['Cr53',0.00011280252269999999], + ['Cr54',2.80789355e-05], + ['Mn55',0.000105699], + ['Ni58',0.000326455285491], + ['Ni60',0.000125749991509], + ['Ni61',5.466265061e-06], + ['Ni62',1.7428844955e-05], + ['Ni64',4.438612984000001e-06], + ['C0',1.87078e-05], + ['Cu63',1.188335835e-05], + ['Cu65',5.301541649999999e-06], + ['Fe54',0.0002497235335], + ['Fe56',0.0039201254222], + ['Fe57',9.05327917e-05], + ['Fe58',1.20482526e-05], + ['Mo100',8.026103567999999e-07], + ['Mo92',1.2066337353000001e-06], + ['Mo94',7.567304339e-07], + ['Mo95',1.3074542481e-06], + ['Mo96',1.3733500081e-06], + ['Mo97',7.892664654000001e-07], + ['Mo98',2.0009247524e-06], + ['Si28',6.287730765095999e-05], + ['Si29',3.1927302805199995e-06], + ['Si30',2.10466206852e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=41.93313, bc='interface') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=86.88175, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=104.17047, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=115.32402, bc='vacuum') +s10 = mcdc.surface('plane-z', z=-121.92, bc='vacuum') +s11 = mcdc.surface('plane-z', z=-92.08002, bc='interface') +s12 = mcdc.surface('plane-z', z=-38.17874, bc='interface') +s13 = mcdc.surface('plane-z', z=38.17874, bc='interface') +s14 = mcdc.surface('plane-z', z=92.08002, bc='interface') +s15 = mcdc.surface('plane-z', z=121.92, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s4 & +s10 & -s11, fill=m5) +c2 = mcdc.cell(-s1 & +s11 & -s12, fill=m2) +c3 = mcdc.cell(-s1 & +s12 & -s13, fill=m1) +c4 = mcdc.cell(-s1 & +s13 & -s14, fill=m2) +c5 = mcdc.cell(+s1 & -s2 & +s11 & -s14, fill=m3) +c6 = mcdc.cell(+s2 & -s3 & +s11 & -s14, fill=m4) +c7 = mcdc.cell(+s3 & -s4 & +s11 & -s14, fill=m5) +c8 = mcdc.cell(-s4 & +s14 & -s15, fill=m5) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-42.0,42.0], y=[-42.0,42.0], z=[0.0,38.2], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-met-inter-002/openmc/generate_materials.py b/icsbep/openmc/pu-met-inter-002/openmc/generate_materials.py new file mode 100644 index 0000000..dd46e82 --- /dev/null +++ b/icsbep/openmc/pu-met-inter-002/openmc/generate_materials.py @@ -0,0 +1,81 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Core region" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.69380e-09) +mat.add_nuclide('Pu239', 1.06299e-03) +mat.add_nuclide('Pu240', 5.03037e-05) +mat.add_nuclide('Pu241', 1.70034e-06) +mat.add_nuclide('Pu242', 1.15592e-07) +mat.add_nuclide('Am241', 2.98613e-06) +mat.add_element('Cr', 9.84199e-03) +mat.add_element('Al', 1.11659e-04) +mat.add_element('Mn', 8.05254e-04) +mat.add_element('Co', 3.71924e-06) +mat.add_element('Ni', 4.08528e-03) +mat.add_element('C', 2.58213e-02) +mat.add_element('Cu', 1.01231e-04) +mat.add_element('Fe', 3.52607e-02) +mat.add_element('Mo', 7.42792e-05) +mat.add_element('Si', 2.79577e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Axial stainless steel" +mat.set_density('sum') +mat.add_element('Cr', 1.57277e-02) +mat.add_element('Mn', 1.56081e-03) +mat.add_element('Co', 3.73582e-06) +mat.add_element('Ni', 6.94657e-03) +mat.add_element('C', 2.35948e-04) +mat.add_element('Cu', 2.98115e-05) +mat.add_element('Fe', 5.55221e-02) +mat.add_element('Mo', 1.52120e-05) +mat.add_element('Si', 9.45490e-04) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Radial stainless steel" +mat.set_density('sum') +mat.add_element('Cr', 1.56286e-02) +mat.add_element('Mn', 1.42057e-03) +mat.add_element('Co', 3.77932e-06) +mat.add_element('Ni', 6.78410e-03) +mat.add_element('C', 2.37106e-04) +mat.add_element('Cu', 5.04052e-05) +mat.add_element('Fe', 5.51964e-02) +mat.add_element('Mo', 4.64023e-05) +mat.add_element('Si', 8.63360e-04) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Iron radial reflector" +mat.set_density('sum') +mat.add_element('Cr', 1.82758e-03) +mat.add_element('Mn', 5.50350e-04) +mat.add_element('Co', 3.77222e-06) +mat.add_element('Ni', 7.61435e-04) +mat.add_element('C', 4.27315e-04) +mat.add_element('Cu', 2.90457e-05) +mat.add_element('Fe', 7.66532e-02) +mat.add_element('Mo', 1.46235e-05) +mat.add_element('Si', 1.45148e-04) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Empty matrix" +mat.set_density('sum') +mat.add_element('Cr', 1.18727e-03) +mat.add_element('Mn', 1.05699e-04) +mat.add_element('Ni', 4.79539e-04) +mat.add_element('C', 1.87078e-05) +mat.add_element('Cu', 1.71849e-05) +mat.add_element('Fe', 4.27243e-03) +mat.add_element('Mo', 8.23697e-06) +mat.add_element('Si', 6.81747e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-met-inter-002/openmc/geometry.xml b/icsbep/openmc/pu-met-inter-002/openmc/geometry.xml new file mode 100644 index 0000000..f5f0ea2 --- /dev/null +++ b/icsbep/openmc/pu-met-inter-002/openmc/geometry.xml @@ -0,0 +1,31 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-met-inter-002/openmc/materials.xml b/icsbep/openmc/pu-met-inter-002/openmc/materials.xml new file mode 100644 index 0000000..123f899 --- /dev/null +++ b/icsbep/openmc/pu-met-inter-002/openmc/materials.xml @@ -0,0 +1,164 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-met-inter-002/openmc/settings.xml b/icsbep/openmc/pu-met-inter-002/openmc/settings.xml new file mode 100644 index 0000000..dfd664f --- /dev/null +++ b/icsbep/openmc/pu-met-inter-002/openmc/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -42 -42 0 + 42 42 38.2 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-1.py b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-1.py new file mode 100644 index 0000000..029cb6f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-1.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.108e-08], + ['Pu239',0.00017472], + ['Pu240',8.5486e-06], + ['Pu242',1.6345e-08], + ['N14',0.00085565], + ['H1',0.064883], + ['O16',0.034948]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5151, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6396, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6396, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-2.py b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-2.py new file mode 100644 index 0000000..2f0a2bb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-2.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.4571e-08], + ['Pu239',0.00022977], + ['Pu240',1.1242e-05], + ['Pu242',2.1495e-08], + ['N14',0.0019726], + ['H1',0.062392], + ['O16',0.036611]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5377, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6622, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6622, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-3.py b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-3.py new file mode 100644 index 0000000..685fc53 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-3.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.8063e-08], + ['Pu239',0.00028482], + ['Pu240',1.3935e-05], + ['Pu242',2.6645e-08], + ['N14',0.0024028], + ['H1',0.061481], + ['O16',0.037347]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5113, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6358, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6358, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-4.py b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-4.py new file mode 100644 index 0000000..dacc11c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-4.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',2.0036e-08], + ['Pu239',0.00031594], + ['Pu240',1.5458e-05], + ['Pu242',2.9556e-08], + ['N14',0.0027146], + ['H1',0.060164], + ['O16',0.037533]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5302, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6547, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6547, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-5.py b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-5.py new file mode 100644 index 0000000..9584427 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-5.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',2.125e-08], + ['Pu239',0.00033509], + ['Pu240',1.6395e-05], + ['Pu242',3.1347e-08], + ['N14',0.002735], + ['H1',0.060371], + ['O16',0.037728]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5302, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6547, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6547, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-6.py b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-6.py new file mode 100644 index 0000000..0dc20ba --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/mcdc/pu-sol-therm-001_case-6.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0785e-08], + ['Pu239',0.00064313], + ['Pu240',3.1466e-05], + ['Pu242',6.0164e-08], + ['N14',0.0033692], + ['H1',0.058646], + ['O16',0.039099]]) +# Material Name: Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5189, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6434, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6434, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..1c5588b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.1080e-08) +mat.add_nuclide('Pu239', 1.7472e-04) +mat.add_nuclide('Pu240', 8.5486e-06) +mat.add_nuclide('Pu241', 5.5623e-07) +mat.add_nuclide('Pu242', 1.6345e-08) +mat.add_nuclide('N14', 8.5565e-04) +mat.add_nuclide('H1', 6.4883e-02) +mat.add_nuclide('O16', 3.4948e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/geometry.xml new file mode 100644 index 0000000..a148a37 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/materials.xml new file mode 100644 index 0000000..22f4ff2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..85bd024 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.4571e-08) +mat.add_nuclide('Pu239', 2.2977e-04) +mat.add_nuclide('Pu240', 1.1242e-05) +mat.add_nuclide('Pu241', 7.3148e-07) +mat.add_nuclide('Pu242', 2.1495e-08) +mat.add_nuclide('N14', 1.9726e-03) +mat.add_nuclide('H1', 6.2392e-02) +mat.add_nuclide('O16', 3.6611e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/geometry.xml new file mode 100644 index 0000000..721559d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/materials.xml new file mode 100644 index 0000000..377b16c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..2b8938e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.8063e-08) +mat.add_nuclide('Pu239', 2.8482e-04) +mat.add_nuclide('Pu240', 1.3935e-05) +mat.add_nuclide('Pu241', 9.0672e-07) +mat.add_nuclide('Pu242', 2.6645e-08) +mat.add_nuclide('N14', 2.4028e-03) +mat.add_nuclide('H1', 6.1481e-02) +mat.add_nuclide('O16', 3.7347e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/geometry.xml new file mode 100644 index 0000000..d892278 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/materials.xml new file mode 100644 index 0000000..5bf8536 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..35b5f91 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 2.0036e-08) +mat.add_nuclide('Pu239', 3.1594e-04) +mat.add_nuclide('Pu240', 1.5458e-05) +mat.add_nuclide('Pu241', 1.0058e-06) +mat.add_nuclide('Pu242', 2.9556e-08) +mat.add_nuclide('N14', 2.7146e-03) +mat.add_nuclide('H1', 6.0164e-02) +mat.add_nuclide('O16', 3.7533e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/geometry.xml new file mode 100644 index 0000000..a91ece3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/materials.xml new file mode 100644 index 0000000..dff9706 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..e877747 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 2.1250e-08) +mat.add_nuclide('Pu239', 3.3509e-04) +mat.add_nuclide('Pu240', 1.6395e-05) +mat.add_nuclide('Pu241', 1.0667e-06) +mat.add_nuclide('Pu242', 3.1347e-08) +mat.add_nuclide('N14', 2.7350e-03) +mat.add_nuclide('H1', 6.0371e-02) +mat.add_nuclide('O16', 3.7728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/geometry.xml new file mode 100644 index 0000000..295d0b3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/materials.xml new file mode 100644 index 0000000..0c52372 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..bbeafb2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0785e-08) +mat.add_nuclide('Pu239', 6.4313e-04) +mat.add_nuclide('Pu240', 3.1466e-05) +mat.add_nuclide('Pu241', 2.0474e-06) +mat.add_nuclide('Pu242', 6.0164e-08) +mat.add_nuclide('N14', 3.3692e-03) +mat.add_nuclide('H1', 5.8646e-02) +mat.add_nuclide('O16', 3.9099e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/geometry.xml new file mode 100644 index 0000000..b567cc7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/materials.xml new file mode 100644 index 0000000..f3b2f88 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-001/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-001/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-1.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-1.py new file mode 100644 index 0000000..19c8ea9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-1.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00012164], + ['Pu240',3.901e-06], + ['N14',0.0013452], + ['H1',0.063772], + ['O16',0.0355], + ['Fe54',1.1912109999999999e-07], + ['Fe56',1.86994652e-06], + ['Fe57',4.3185219999999997e-08], + ['Fe58',5.74716e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-2.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-2.py new file mode 100644 index 0000000..6a35844 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-2.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00012549], + ['Pu240',4.0246e-06], + ['N14',0.0015831], + ['H1',0.063356], + ['O16',0.035895], + ['Fe54',1.7143385e-07], + ['Fe56',2.6911448200000003e-06], + ['Fe57',6.215027000000001e-08], + ['Fe58',8.271060000000001e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-3.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-3.py new file mode 100644 index 0000000..ca3bf5d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-3.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00013689], + ['Pu240',4.3902e-06], + ['N14',0.0020104], + ['H1',0.061779], + ['O16',0.036198], + ['Fe54',1.5441905500000002e-07], + ['Fe56',2.4240489260000002e-06], + ['Fe57',5.5981861e-08], + ['Fe58',7.450158e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-4.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-4.py new file mode 100644 index 0000000..1b817b7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-4.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00014556], + ['Pu240',4.668e-06], + ['N14',0.0023018], + ['H1',0.06121100000000001], + ['O16',0.03666], + ['Fe54',1.2101488000000002e-07], + ['Fe56',1.8996748160000001e-06], + ['Fe57',4.3871776000000005e-08], + ['Fe58',5.838528e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-5.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-5.py new file mode 100644 index 0000000..00200a9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-5.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00015456], + ['Pu240',4.9568e-06], + ['N14',0.0026223], + ['H1',0.060707], + ['O16',0.037228], + ['Fe54',1.2416533500000002e-07], + ['Fe56',1.9491302220000003e-06], + ['Fe57',4.5013917000000005e-08], + ['Fe58',5.990526000000001e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-6.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-6.py new file mode 100644 index 0000000..58b98e6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-6.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00017111], + ['Pu240',5.4875e-06], + ['N14',0.0031274], + ['H1',0.058902], + ['O16',0.037623], + ['Fe54',1.3739841500000002e-07], + ['Fe56',2.1568612780000004e-06], + ['Fe57',4.9811333000000005e-08], + ['Fe58',6.628974e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-7.py b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-7.py new file mode 100644 index 0000000..94d25f9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/mcdc/pu-sol-therm-002_case-7.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00018814], + ['Pu240',6.0338e-06], + ['N14',0.0034866999999999997], + ['H1',0.058109], + ['O16',0.03816], + ['Fe54',1.4937482e-07], + ['Fe56',2.3448652240000003e-06], + ['Fe57',5.415316400000001e-08], + ['Fe58',7.206792e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.3399, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.4669, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=45.4669, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..bbfccab --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.2164e-04) +mat.add_nuclide('Pu240', 3.9010e-06) +mat.add_nuclide('N14', 1.3452e-03) +mat.add_nuclide('H1', 6.3772e-02) +mat.add_nuclide('O16', 3.5500e-02) +mat.add_element('Fe', 2.0380e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/geometry.xml new file mode 100644 index 0000000..ae225c0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/materials.xml new file mode 100644 index 0000000..8881911 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..2818105 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.2549e-04) +mat.add_nuclide('Pu240', 4.0246e-06) +mat.add_nuclide('N14', 1.5831e-03) +mat.add_nuclide('H1', 6.3356e-02) +mat.add_nuclide('O16', 3.5895e-02) +mat.add_element('Fe', 2.9330e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/geometry.xml new file mode 100644 index 0000000..c3aaf4c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/materials.xml new file mode 100644 index 0000000..c6e1e56 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..b442583 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.3689e-04) +mat.add_nuclide('Pu240', 4.3902e-06) +mat.add_nuclide('N14', 2.0104e-03) +mat.add_nuclide('H1', 6.1779e-02) +mat.add_nuclide('O16', 3.6198e-02) +mat.add_element('Fe', 2.6419e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/geometry.xml new file mode 100644 index 0000000..2e31487 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/materials.xml new file mode 100644 index 0000000..6b13560 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..664da31 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.4556e-04) +mat.add_nuclide('Pu240', 4.6680e-06) +mat.add_nuclide('N14', 2.3018e-03) +mat.add_nuclide('H1', 6.1211e-02) +mat.add_nuclide('O16', 3.6660e-02) +mat.add_element('Fe', 2.0704e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/geometry.xml new file mode 100644 index 0000000..727162f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/materials.xml new file mode 100644 index 0000000..59927ef --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..8ab42aa --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.5456e-04) +mat.add_nuclide('Pu240', 4.9568e-06) +mat.add_nuclide('N14', 2.6223e-03) +mat.add_nuclide('H1', 6.0707e-02) +mat.add_nuclide('O16', 3.7228e-02) +mat.add_element('Fe', 2.1243e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/geometry.xml new file mode 100644 index 0000000..67305df --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/materials.xml new file mode 100644 index 0000000..232d7fa --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..6fd7ebc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.7111e-04) +mat.add_nuclide('Pu240', 5.4875e-06) +mat.add_nuclide('N14', 3.1274e-03) +mat.add_nuclide('H1', 5.8902e-02) +mat.add_nuclide('O16', 3.7623e-02) +mat.add_element('Fe', 2.3507e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/geometry.xml new file mode 100644 index 0000000..429292a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/materials.xml new file mode 100644 index 0000000..e92a55a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..03caf6d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.8814e-04) +mat.add_nuclide('Pu240', 6.0338e-06) +mat.add_nuclide('N14', 3.4867e-03) +mat.add_nuclide('H1', 5.8109e-02) +mat.add_nuclide('O16', 3.8160e-02) +mat.add_element('Fe', 2.5556e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/geometry.xml new file mode 100644 index 0000000..ced7d3a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/materials.xml new file mode 100644 index 0000000..a1cc55e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-002/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-002/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-1.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-1.py new file mode 100644 index 0000000..657de16 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-1.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.2461e-05], + ['Pu240',1.4712e-06], + ['N14',0.00084206], + ['H1',0.064976], + ['O16',0.034761], + ['Fe54',7.815349500000001e-08], + ['Fe56',1.226842734e-06], + ['Fe57',2.8333149e-08], + ['Fe58',3.770622000000001e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.5156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.6426, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.6426, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-2.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-2.py new file mode 100644 index 0000000..61cc361 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-2.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.4936e-05], + ['Pu240',1.5153e-06], + ['N14',0.0011315], + ['H1',0.064208], + ['O16',0.035106], + ['Fe54',7.374051999999999e-08], + ['Fe56',1.1575684639999999e-06], + ['Fe57',2.6733304e-08], + ['Fe58',3.5577119999999995e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.5156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.6426, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.6426, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-3.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-3.py new file mode 100644 index 0000000..99d9f0c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-3.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.135e-05], + ['Pu240',2.9296e-06], + ['N14',0.0012626], + ['H1',0.063843], + ['O16',0.035266], + ['Fe54',6.4920415e-08], + ['Fe56',1.0191116780000001e-06], + ['Fe57',2.3535733e-08], + ['Fe58',3.132174e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.5156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.6426, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.6426, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-4.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-4.py new file mode 100644 index 0000000..f525daf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-4.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.3034e-05], + ['Pu240',2.9836e-06], + ['N14',0.0015151], + ['H1',0.063424], + ['O16',0.035692], + ['Fe54',8.886738000000001e-08], + ['Fe56',1.395027816e-06], + ['Fe57',3.2217276000000005e-08], + ['Fe58',4.287528e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.5156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.6426, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.6426, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-5.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-5.py new file mode 100644 index 0000000..d60142e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-5.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.9209e-05], + ['Pu240',3.1817000000000004e-06], + ['N14',0.001991], + ['H1',0.06216900000000001], + ['O16',0.036267], + ['Fe54',1.61982485e-07], + ['Fe56',2.542778602e-06], + ['Fe57',5.8723847000000004e-08], + ['Fe58',7.815066e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.5156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.6426, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.6426, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-6.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-6.py new file mode 100644 index 0000000..c7948d8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-6.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.0001076], + ['Pu240',3.4509000000000003e-06], + ['N14',0.0026175], + ['H1',0.060559], + ['O16',0.037045], + ['Fe54',1.67652135e-07], + ['Fe56',2.6317799820000004e-06], + ['Fe57',6.0779277e-08], + ['Fe58',8.088606e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.5156, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.6426, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.6426, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-7.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-7.py new file mode 100644 index 0000000..d17a929 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-7.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.7811e-05], + ['Pu240',2.8161e-06], + ['N14',0.00090422], + ['H1',0.064783], + ['O16',0.034833], + ['Fe54',7.1852585e-08], + ['Fe56',1.127931922e-06], + ['Fe57',2.6048866999999998e-08], + ['Fe58',3.4666260000000004e-09]]) +# Material Name: 2S (1100) aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.2487, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.3777, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.3777, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-8.py b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-8.py new file mode 100644 index 0000000..2f5252c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/mcdc/pu-sol-therm-003_case-8.py @@ -0,0 +1,73 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.9837e-05], + ['Pu240',2.8811e-06], + ['N14',0.001214], + ['H1',0.064172], + ['O16',0.035307], + ['Fe54',8.0678535e-08], + ['Fe56',1.266480462e-06], + ['Fe57',2.9248557e-08], + ['Fe58',3.892446e-09]]) +# Material Name: 2S (1100) aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.2487, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=16.3777, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=46.3777, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..0121c45 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.2461e-05) +mat.add_nuclide('Pu240', 1.4712e-06) +mat.add_nuclide('N14', 8.4206e-04) +mat.add_nuclide('H1', 6.4976e-02) +mat.add_nuclide('O16', 3.4761e-02) +mat.add_element('Fe', 1.3371e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/geometry.xml new file mode 100644 index 0000000..8aab431 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/materials.xml new file mode 100644 index 0000000..c28c572 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..f0f6471 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.4936e-05) +mat.add_nuclide('Pu240', 1.5153e-06) +mat.add_nuclide('N14', 1.1315e-03) +mat.add_nuclide('H1', 6.4208e-02) +mat.add_nuclide('O16', 3.5106e-02) +mat.add_element('Fe', 1.2616e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/geometry.xml new file mode 100644 index 0000000..370cf36 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/materials.xml new file mode 100644 index 0000000..68a05b1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..e3d72b8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.1350e-05) +mat.add_nuclide('Pu240', 2.9296e-06) +mat.add_nuclide('N14', 1.2626e-03) +mat.add_nuclide('H1', 6.3843e-02) +mat.add_nuclide('O16', 3.5266e-02) +mat.add_element('Fe', 1.1107e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/geometry.xml new file mode 100644 index 0000000..54238ac --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/materials.xml new file mode 100644 index 0000000..9c43d90 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..b678b7a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.3034e-05) +mat.add_nuclide('Pu240', 2.9836e-06) +mat.add_nuclide('N14', 1.5151e-03) +mat.add_nuclide('H1', 6.3424e-02) +mat.add_nuclide('O16', 3.5692e-02) +mat.add_element('Fe', 1.5204e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/geometry.xml new file mode 100644 index 0000000..f6c6e6d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/materials.xml new file mode 100644 index 0000000..cf3a9d3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..2367179 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.9209e-05) +mat.add_nuclide('Pu240', 3.1817e-06) +mat.add_nuclide('N14', 1.9910e-03) +mat.add_nuclide('H1', 6.2169e-02) +mat.add_nuclide('O16', 3.6267e-02) +mat.add_element('Fe', 2.7713e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/geometry.xml new file mode 100644 index 0000000..8a37581 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/materials.xml new file mode 100644 index 0000000..dc6ddd7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..7d59e0e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.0760e-04) +mat.add_nuclide('Pu240', 3.4509e-06) +mat.add_nuclide('N14', 2.6175e-03) +mat.add_nuclide('H1', 6.0559e-02) +mat.add_nuclide('O16', 3.7045e-02) +mat.add_element('Fe', 2.8683e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/geometry.xml new file mode 100644 index 0000000..94b5d8c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/materials.xml new file mode 100644 index 0000000..c4d334c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..b2a71e3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.7811e-05) +mat.add_nuclide('Pu240', 2.8161e-06) +mat.add_nuclide('N14', 9.0422e-04) +mat.add_nuclide('H1', 6.4783e-02) +mat.add_nuclide('O16', 3.4833e-02) +mat.add_element('Fe', 1.2293e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "2S (1100) aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/geometry.xml new file mode 100644 index 0000000..d18ae1c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/materials.xml new file mode 100644 index 0000000..9870c1a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..4efea70 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.9837e-05) +mat.add_nuclide('Pu240', 2.8811e-06) +mat.add_nuclide('N14', 1.2140e-03) +mat.add_nuclide('H1', 6.4172e-02) +mat.add_nuclide('O16', 3.5307e-02) +mat.add_element('Fe', 1.3803e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "2S (1100) aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/geometry.xml new file mode 100644 index 0000000..f1b8005 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/materials.xml new file mode 100644 index 0000000..4778dd6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-003/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-003/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-1.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-1.py new file mode 100644 index 0000000..9599436 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-1.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.5821e-05], + ['Pu240',3.5587e-07], + ['N14',0.00075562], + ['H1',0.064964], + ['O16',0.034503], + ['Fe54',9.139242e-08], + ['Fe56',1.434665544e-06], + ['Fe57',3.3132684e-08], + ['Fe58',4.409352e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-10.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-10.py new file mode 100644 index 0000000..77695f7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-10.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.6298e-05], + ['Pu240',2.7676e-06], + ['N14',0.003006], + ['H1',0.059494], + ['O16',0.03744], + ['Fe54',9.139242e-08], + ['Fe56',1.434665544e-06], + ['Fe57',3.3132684e-08], + ['Fe58',4.409352e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-11.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-11.py new file mode 100644 index 0000000..4412e8b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-11.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.6012e-05], + ['Pu240',3.0791e-06], + ['N14',0.0039626], + ['H1',0.056873], + ['O16',0.038541], + ['Fe54',9.264909500000001e-08], + ['Fe56',1.454392654e-06], + ['Fe57',3.3588269000000006e-08], + ['Fe58',4.4699820000000005e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-12.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-12.py new file mode 100644 index 0000000..7ff0436 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-12.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.185e-05], + ['Pu240',2.3043e-06], + ['N14',0.0011169], + ['H1',0.064144], + ['O16',0.035013], + ['Fe54',7.1221325e-08], + ['Fe56',1.11802249e-06], + ['Fe57',2.5820015e-08], + ['Fe58',3.4361700000000006e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-13.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-13.py new file mode 100644 index 0000000..9b72ef6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-13.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.1207e-05], + ['Pu240',2.5186e-06], + ['N14',0.001081], + ['H1',0.064304], + ['O16',0.035002], + ['Fe54',8.823612e-08], + ['Fe56',1.3851183839999999e-06], + ['Fe57',3.1988424e-08], + ['Fe58',4.2570719999999995e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-2.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-2.py new file mode 100644 index 0000000..e1ffcae --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-2.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.5921e-05], + ['Pu240',3.5641e-07], + ['N14',0.0010392], + ['H1',0.064397], + ['O16',0.034929], + ['Fe54',9.391161500000001e-08], + ['Fe56',1.474211518e-06], + ['Fe57',3.4045973e-08], + ['Fe58',4.530894e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-3.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-3.py new file mode 100644 index 0000000..8376cc6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-3.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.8151e-05], + ['Pu240',3.6847e-07], + ['N14',0.0013354], + ['H1',0.063696], + ['O16',0.035324], + ['Fe54',9.832459e-08], + ['Fe56',1.543485788e-06], + ['Fe57',3.5645818e-08], + ['Fe58',4.743804e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-4.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-4.py new file mode 100644 index 0000000..db6e8cf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-4.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.0381e-05], + ['Pu240',3.8053e-07], + ['N14',0.0018211], + ['H1',0.062562], + ['O16',0.035975], + ['Fe54',1.0336298000000002e-07], + ['Fe56',1.6225777359999998e-06], + ['Fe57',3.7472396e-08], + ['Fe58',4.986888e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-5.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-5.py new file mode 100644 index 0000000..4581070 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-5.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.8256e-05], + ['Pu240',1.2177e-06], + ['N14',0.0010635], + ['H1',0.064299], + ['O16',0.034947], + ['Fe54',5.924491999999999e-08], + ['Fe56',9.30018544e-07], + ['Fe57',2.1478183999999998e-08], + ['Fe58',2.858352e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-6.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-6.py new file mode 100644 index 0000000..24804fd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-6.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.98e-05], + ['Pu240',2.2385e-06], + ['N14',0.0008488600000000001], + ['H1',0.064732], + ['O16',0.034632], + ['Fe54',6.933339e-08], + ['Fe56',1.088385948e-06], + ['Fe57',2.5135578e-08], + ['Fe58',3.345084e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-7.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-7.py new file mode 100644 index 0000000..04820d6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-7.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.2167e-05], + ['Pu240',2.3144e-06], + ['N14',0.0010635], + ['H1',0.064353], + ['O16',0.034984], + ['Fe54',8.067269e-08], + ['Fe56',1.266388708e-06], + ['Fe57',2.9246438e-08], + ['Fe58',3.8921639999999995e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-8.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-8.py new file mode 100644 index 0000000..221354e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-8.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.3095e-05], + ['Pu240',2.3442e-06], + ['N14',0.0013889], + ['H1',0.063518], + ['O16',0.035382], + ['Fe54',7.1221325e-08], + ['Fe56',1.11802249e-06], + ['Fe57',2.5820015e-08], + ['Fe58',3.43617e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-9.py b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-9.py new file mode 100644 index 0000000..c3a6818 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/mcdc/pu-sol-therm-004_case-9.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.7122e-05], + ['Pu240',2.4733e-06], + ['N14',0.0020202], + ['H1',0.062101], + ['O16',0.03626], + ['Fe54',7.56343e-08], + ['Fe56',1.18729676e-06], + ['Fe57',2.7419860000000002e-08], + ['Fe58',3.64908e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..3968291 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.5821e-05) +mat.add_nuclide('Pu240', 3.5587e-07) +mat.add_nuclide('N14', 7.5562e-04) +mat.add_nuclide('H1', 6.4964e-02) +mat.add_nuclide('O16', 3.4503e-02) +mat.add_element('Fe', 1.5636e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/geometry.xml new file mode 100644 index 0000000..abb1f88 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/materials.xml new file mode 100644 index 0000000..032dcac --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-10/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..7b9ed00 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.6298e-05) +mat.add_nuclide('Pu240', 2.7676e-06) +mat.add_nuclide('N14', 3.0060e-03) +mat.add_nuclide('H1', 5.9494e-02) +mat.add_nuclide('O16', 3.7440e-02) +mat.add_element('Fe', 1.5636e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-10/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/geometry.xml new file mode 100644 index 0000000..da09ef7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-10/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/materials.xml new file mode 100644 index 0000000..6500a1f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-10/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-10/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-11/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/generate_materials.py new file mode 100644 index 0000000..65ab415 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.6012e-05) +mat.add_nuclide('Pu240', 3.0791e-06) +mat.add_nuclide('N14', 3.9626e-03) +mat.add_nuclide('H1', 5.6873e-02) +mat.add_nuclide('O16', 3.8541e-02) +mat.add_element('Fe', 1.5851e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-11/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/geometry.xml new file mode 100644 index 0000000..85dd43d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-11/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/materials.xml new file mode 100644 index 0000000..721839c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-11/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-11/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-12/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/generate_materials.py new file mode 100644 index 0000000..dd442ba --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.1850e-05) +mat.add_nuclide('Pu240', 2.3043e-06) +mat.add_nuclide('N14', 1.1169e-03) +mat.add_nuclide('H1', 6.4144e-02) +mat.add_nuclide('O16', 3.5013e-02) +mat.add_element('Fe', 1.2185e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-12/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/geometry.xml new file mode 100644 index 0000000..7343415 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-12/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/materials.xml new file mode 100644 index 0000000..384c77a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-12/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-12/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-13/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/generate_materials.py new file mode 100644 index 0000000..7b9773d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.1207e-05) +mat.add_nuclide('Pu240', 2.5186e-06) +mat.add_nuclide('N14', 1.0810e-03) +mat.add_nuclide('H1', 6.4304e-02) +mat.add_nuclide('O16', 3.5002e-02) +mat.add_element('Fe', 1.5096e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-13/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/geometry.xml new file mode 100644 index 0000000..13eced2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-13/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/materials.xml new file mode 100644 index 0000000..c075607 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-13/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-13/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..354b6b5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.5921e-05) +mat.add_nuclide('Pu240', 3.5641e-07) +mat.add_nuclide('N14', 1.0392e-03) +mat.add_nuclide('H1', 6.4397e-02) +mat.add_nuclide('O16', 3.4929e-02) +mat.add_element('Fe', 1.6067e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/geometry.xml new file mode 100644 index 0000000..fc8ee19 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/materials.xml new file mode 100644 index 0000000..9dcdb47 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..fb0d10b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.8151e-05) +mat.add_nuclide('Pu240', 3.6847e-07) +mat.add_nuclide('N14', 1.3354e-03) +mat.add_nuclide('H1', 6.3696e-02) +mat.add_nuclide('O16', 3.5324e-02) +mat.add_element('Fe', 1.6822e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/geometry.xml new file mode 100644 index 0000000..d848f54 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/materials.xml new file mode 100644 index 0000000..98cad5e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..4437d74 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.0381e-05) +mat.add_nuclide('Pu240', 3.8053e-07) +mat.add_nuclide('N14', 1.8211e-03) +mat.add_nuclide('H1', 6.2562e-02) +mat.add_nuclide('O16', 3.5975e-02) +mat.add_element('Fe', 1.7684e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/geometry.xml new file mode 100644 index 0000000..9043000 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/materials.xml new file mode 100644 index 0000000..ced0e4b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..24a1451 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.8256e-05) +mat.add_nuclide('Pu240', 1.2177e-06) +mat.add_nuclide('N14', 1.0635e-03) +mat.add_nuclide('H1', 6.4299e-02) +mat.add_nuclide('O16', 3.4947e-02) +mat.add_element('Fe', 1.0136e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/geometry.xml new file mode 100644 index 0000000..7ef98d3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/materials.xml new file mode 100644 index 0000000..ad70ad7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..403e4bf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.9800e-05) +mat.add_nuclide('Pu240', 2.2385e-06) +mat.add_nuclide('N14', 8.4886e-04) +mat.add_nuclide('H1', 6.4732e-02) +mat.add_nuclide('O16', 3.4632e-02) +mat.add_element('Fe', 1.1862e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/geometry.xml new file mode 100644 index 0000000..f2fc27f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/materials.xml new file mode 100644 index 0000000..e057327 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..f617173 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.2167e-05) +mat.add_nuclide('Pu240', 2.3144e-06) +mat.add_nuclide('N14', 1.0635e-03) +mat.add_nuclide('H1', 6.4353e-02) +mat.add_nuclide('O16', 3.4984e-02) +mat.add_element('Fe', 1.3802e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/geometry.xml new file mode 100644 index 0000000..b9c58ec --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/materials.xml new file mode 100644 index 0000000..92442e0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..007b3bf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.3095e-05) +mat.add_nuclide('Pu240', 2.3442e-06) +mat.add_nuclide('N14', 1.3889e-03) +mat.add_nuclide('H1', 6.3518e-02) +mat.add_nuclide('O16', 3.5382e-02) +mat.add_element('Fe', 1.2185e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/geometry.xml new file mode 100644 index 0000000..8dac119 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/materials.xml new file mode 100644 index 0000000..81cfc42 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-9/generate_materials.py b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..16e06d8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.7122e-05) +mat.add_nuclide('Pu240', 2.4733e-06) +mat.add_nuclide('N14', 2.0202e-03) +mat.add_nuclide('H1', 6.2101e-02) +mat.add_nuclide('O16', 3.6260e-02) +mat.add_element('Fe', 1.2940e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-9/geometry.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/geometry.xml new file mode 100644 index 0000000..5574b97 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-9/materials.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/materials.xml new file mode 100644 index 0000000..b08cb19 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-004/openmc/case-9/settings.xml b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-004/openmc/case-9/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-1.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-1.py new file mode 100644 index 0000000..a3f4588 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-1.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.1668e-05], + ['Pu240',3.0124e-06], + ['N14',0.00084973], + ['H1',0.0647], + ['O16',0.034624], + ['Fe54',8.067269e-08], + ['Fe56',1.266388708e-06], + ['Fe57',2.9246437999999997e-08], + ['Fe58',3.8921639999999995e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-2.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-2.py new file mode 100644 index 0000000..5d66d54 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-2.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.3819e-05], + ['Pu240',3.1029e-06], + ['N14',0.0011587], + ['H1',0.064054], + ['O16',0.035077], + ['Fe54',4.9791801499999995e-08], + ['Fe56',7.816247998e-07], + ['Fe57',1.80511253e-08], + ['Fe58',2.4022734e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-3.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-3.py new file mode 100644 index 0000000..47fcbfc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-3.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.597e-05], + ['Pu240',3.1933e-06], + ['N14',0.0014258], + ['H1',0.063387], + ['O16',0.035416], + ['Fe54',5.4204191999999995e-08], + ['Fe56',8.508898944e-07], + ['Fe57',1.96507584e-08], + ['Fe58',2.6151552e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-4.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-4.py new file mode 100644 index 0000000..7a4272d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-4.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.1071e-05], + ['Pu240',3.4077000000000004e-06], + ['N14',0.0020464], + ['H1',0.062039], + ['O16',0.036305], + ['Fe54',6.11387e-08], + ['Fe56',9.5974684e-07], + ['Fe57',2.216474e-08], + ['Fe58',2.94972e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-5.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-5.py new file mode 100644 index 0000000..d6522b1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-5.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.7113e-05], + ['Pu240',3.6617e-06], + ['N14',0.0026456], + ['H1',0.060463], + ['O16',0.037027], + ['Fe54',6.5551675e-08], + ['Fe56',1.02902111e-06], + ['Fe57',2.3764585e-08], + ['Fe58',3.16263e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-6.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-6.py new file mode 100644 index 0000000..3650410 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-6.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.3035e-05], + ['Pu240',3.9106e-06], + ['N14',0.0032555999999999996], + ['H1',0.058932000000000005], + ['O16',0.037799], + ['Fe54',7.9416015e-08], + ['Fe56',1.246661598e-06], + ['Fe57',2.8790853000000002e-08], + ['Fe58',3.831534e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-7.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-7.py new file mode 100644 index 0000000..f9f3ed7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-7.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.888500000000001e-05], + ['Pu240',4.1565e-06], + ['N14',0.0037383], + ['H1',0.057412], + ['O16',0.038258], + ['Fe54',7.9416015e-08], + ['Fe56',1.246661598e-06], + ['Fe57',2.8790853000000002e-08], + ['Fe58',3.831534e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-8.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-8.py new file mode 100644 index 0000000..107dc05 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-8.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.3646e-05], + ['Pu240',3.3753999999999995e-06], + ['N14',0.0012286], + ['H1',0.063977], + ['O16',0.035214], + ['Fe54',6.807087e-08], + ['Fe56',1.068567084e-06], + ['Fe57',2.4677874000000004e-08], + ['Fe58',3.2841720000000005e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-9.py b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-9.py new file mode 100644 index 0000000..06e1cad --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/mcdc/pu-sol-therm-005_case-9.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',7.6705e-05], + ['Pu240',3.5156e-06], + ['N14',0.0015345], + ['H1',0.06329], + ['O16',0.035642], + ['Fe54',6.428915500000001e-08], + ['Fe56',1.0092022460000001e-06], + ['Fe57',2.3306881e-08], + ['Fe58',3.101718e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.7865, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=17.9135, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=47.9135, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..9c26607 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.1668e-05) +mat.add_nuclide('Pu240', 3.0124e-06) +mat.add_nuclide('N14', 8.4973e-04) +mat.add_nuclide('H1', 6.4700e-02) +mat.add_nuclide('O16', 3.4624e-02) +mat.add_element('Fe', 1.3802e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/geometry.xml new file mode 100644 index 0000000..77c98d0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/materials.xml new file mode 100644 index 0000000..c5f27f8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..0d0f719 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.3819e-05) +mat.add_nuclide('Pu240', 3.1029e-06) +mat.add_nuclide('N14', 1.1587e-03) +mat.add_nuclide('H1', 6.4054e-02) +mat.add_nuclide('O16', 3.5077e-02) +mat.add_element('Fe', 8.5187e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/geometry.xml new file mode 100644 index 0000000..daecefe --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/materials.xml new file mode 100644 index 0000000..60fc96d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..ff644c1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.5970e-05) +mat.add_nuclide('Pu240', 3.1933e-06) +mat.add_nuclide('N14', 1.4258e-03) +mat.add_nuclide('H1', 6.3387e-02) +mat.add_nuclide('O16', 3.5416e-02) +mat.add_element('Fe', 9.2736e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/geometry.xml new file mode 100644 index 0000000..3c3aa48 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/materials.xml new file mode 100644 index 0000000..d701004 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..92e67ed --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.1071e-05) +mat.add_nuclide('Pu240', 3.4077e-06) +mat.add_nuclide('N14', 2.0464e-03) +mat.add_nuclide('H1', 6.2039e-02) +mat.add_nuclide('O16', 3.6305e-02) +mat.add_element('Fe', 1.0460e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/geometry.xml new file mode 100644 index 0000000..f3e9ab0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/materials.xml new file mode 100644 index 0000000..70c26ae --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..3694afd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.7113e-05) +mat.add_nuclide('Pu240', 3.6617e-06) +mat.add_nuclide('N14', 2.6456e-03) +mat.add_nuclide('H1', 6.0463e-02) +mat.add_nuclide('O16', 3.7027e-02) +mat.add_element('Fe', 1.1215e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/geometry.xml new file mode 100644 index 0000000..0dd8d52 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/materials.xml new file mode 100644 index 0000000..7b2c6dd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..b8b4141 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.3035e-05) +mat.add_nuclide('Pu240', 3.9106e-06) +mat.add_nuclide('N14', 3.2556e-03) +mat.add_nuclide('H1', 5.8932e-02) +mat.add_nuclide('O16', 3.7799e-02) +mat.add_element('Fe', 1.3587e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/geometry.xml new file mode 100644 index 0000000..6645871 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/materials.xml new file mode 100644 index 0000000..08406da --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..76cb424 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.8885e-05) +mat.add_nuclide('Pu240', 4.1565e-06) +mat.add_nuclide('N14', 3.7383e-03) +mat.add_nuclide('H1', 5.7412e-02) +mat.add_nuclide('O16', 3.8258e-02) +mat.add_element('Fe', 1.3587e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/geometry.xml new file mode 100644 index 0000000..652aff2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/materials.xml new file mode 100644 index 0000000..0e6c7a3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..85c5d3f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.3646e-05) +mat.add_nuclide('Pu240', 3.3754e-06) +mat.add_nuclide('N14', 1.2286e-03) +mat.add_nuclide('H1', 6.3977e-02) +mat.add_nuclide('O16', 3.5214e-02) +mat.add_element('Fe', 1.1646e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/geometry.xml new file mode 100644 index 0000000..8b42f7d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/materials.xml new file mode 100644 index 0000000..4d5cdbf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-9/generate_materials.py b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..36df412 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 7.6705e-05) +mat.add_nuclide('Pu240', 3.5156e-06) +mat.add_nuclide('N14', 1.5345e-03) +mat.add_nuclide('H1', 6.3290e-02) +mat.add_nuclide('O16', 3.5642e-02) +mat.add_element('Fe', 1.0999e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-9/geometry.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/geometry.xml new file mode 100644 index 0000000..2c054e0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-9/materials.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/materials.xml new file mode 100644 index 0000000..42db6cc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-005/openmc/case-9/settings.xml b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-005/openmc/case-9/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-1.py b/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-1.py new file mode 100644 index 0000000..b8bc581 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-1.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.0526e-05], + ['Pu240',1.9411e-06], + ['N14',0.0011266], + ['H1',0.064226], + ['O16',0.035054], + ['Fe54',5.5464374e-08], + ['Fe56',8.706720568e-07], + ['Fe57',2.01076148e-08], + ['Fe58',2.6759544e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.0416, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.1686, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=49.1686, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-2.py b/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-2.py new file mode 100644 index 0000000..2ee93ee --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-2.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.2381e-05], + ['Pu240',2.0006e-06], + ['N14',0.0014277], + ['H1',0.063492], + ['O16',0.035444], + ['Fe54',5.9244920000000006e-08], + ['Fe56',9.30018544e-07], + ['Fe57',2.1478183999999998e-08], + ['Fe58',2.858352e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.0416, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.1686, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=49.1686, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-3.py b/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-3.py new file mode 100644 index 0000000..56fd154 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/mcdc/pu-sol-therm-006_case-3.py @@ -0,0 +1,74 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.5822e-05], + ['Pu240',2.1109e-06], + ['N14',0.002059], + ['H1',0.06188], + ['O16',0.036223], + ['Fe54',6.050744000000001e-08], + ['Fe56',9.49837408e-07], + ['Fe57',2.1935888000000003e-08], + ['Fe58',2.919264e-09]]) +# Material Name: 347 stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Water at 27 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066622], + ['O16',0.033311]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.0416, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.1686, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=49.1686, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..1cfb8e9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.0526e-05) +mat.add_nuclide('Pu240', 1.9411e-06) +mat.add_nuclide('N14', 1.1266e-03) +mat.add_nuclide('H1', 6.4226e-02) +mat.add_nuclide('O16', 3.5054e-02) +mat.add_element('Fe', 9.4892e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/geometry.xml new file mode 100644 index 0000000..add1144 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/materials.xml new file mode 100644 index 0000000..0ba20ef --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..9d87a2f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.2381e-05) +mat.add_nuclide('Pu240', 2.0006e-06) +mat.add_nuclide('N14', 1.4277e-03) +mat.add_nuclide('H1', 6.3492e-02) +mat.add_nuclide('O16', 3.5444e-02) +mat.add_element('Fe', 1.0136e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/geometry.xml new file mode 100644 index 0000000..bb729d1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/materials.xml new file mode 100644 index 0000000..e60be17 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..fc4f24b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/generate_materials.py @@ -0,0 +1,33 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.5822e-05) +mat.add_nuclide('Pu240', 2.1109e-06) +mat.add_nuclide('N14', 2.0590e-03) +mat.add_nuclide('H1', 6.1880e-02) +mat.add_nuclide('O16', 3.6223e-02) +mat.add_element('Fe', 1.0352e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 27 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6622e-02) +mat.add_nuclide('O16', 3.3311e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/geometry.xml new file mode 100644 index 0000000..eca64bd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/materials.xml new file mode 100644 index 0000000..f2f4a24 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-006/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-006/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-10.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-10.py new file mode 100644 index 0000000..7f67491 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-10.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.4192000000000002e-08], + ['Pu239',0.00022379000000000002], + ['Pu240',1.0949e-05], + ['Pu242',2.0935e-08], + ['N14',0.0011703], + ['H1',0.063783], + ['O16',0.035288]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.8371, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-2.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-2.py new file mode 100644 index 0000000..0d17aed --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-2.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.5214e-08], + ['Pu239',0.00055529], + ['Pu240',2.7168e-05], + ['Pu242',5.194700000000001e-08], + ['N14',0.002632], + ['H1',0.06083299999999999], + ['O16',0.038165]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.8271, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-3.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-3.py new file mode 100644 index 0000000..b39adcf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-3.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.3545e-08], + ['Pu239',0.00052896], + ['Pu240',2.588e-05], + ['Pu242',4.9484e-08], + ['N14',0.0026058], + ['H1',0.06028700000000001], + ['O16',0.037771]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.8371, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-5.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-5.py new file mode 100644 index 0000000..871683c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-5.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.5209e-08], + ['Pu239',0.00023983], + ['Pu240',1.1734e-05], + ['Pu242',2.2436e-08], + ['N14',0.0011898], + ['H1',0.064161], + ['O16',0.03556]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.974, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-6.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-6.py new file mode 100644 index 0000000..7f61799 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-6.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.5406e-08], + ['Pu239',0.00024293999999999997], + ['Pu240',1.1886e-05], + ['Pu242',2.2727e-08], + ['N14',0.0012577], + ['H1',0.063655], + ['O16',0.035483]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.6719, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-7.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-7.py new file mode 100644 index 0000000..18a75b5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-7.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.5194e-08], + ['Pu239',0.00023958999999999997], + ['Pu240',1.1722e-05], + ['Pu242',2.2413e-08], + ['N14',0.0012616], + ['H1',0.063671], + ['O16',0.035494]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.974, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-8.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-8.py new file mode 100644 index 0000000..a33d17c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-8.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.5421e-08], + ['Pu239',0.00024318], + ['Pu240',1.1898e-05], + ['Pu242',2.2749e-08], + ['N14',0.0013791], + ['H1',0.062853], + ['O16',0.035386]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.905, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-9.py b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-9.py new file mode 100644 index 0000000..f5fbbf4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/mcdc/pu-sol-therm-007_case-9.py @@ -0,0 +1,75 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.5421e-08], + ['Pu239',0.00024318], + ['Pu240',1.1898e-05], + ['Pu242',2.2749e-08], + ['N14',0.001385], + ['H1',0.063152], + ['O16',0.03555]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +# Material Name: Water at 25 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066655], + ['O16',0.033327]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.5603, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=14.6848, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=44.6848, bc='vacuum') +s4 = mcdc.surface('plane-z', z=10.4502, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s4, fill=m1) +c2 = mcdc.cell(-s1 & +s4, fill=mvoid) +c3 = mcdc.cell(+s1 & -s2, fill=m2) +c4 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-10/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..c465a98 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.4192e-08) +mat.add_nuclide('Pu239', 2.2379e-04) +mat.add_nuclide('Pu240', 1.0949e-05) +mat.add_nuclide('Pu241', 7.1243e-07) +mat.add_nuclide('Pu242', 2.0935e-08) +mat.add_nuclide('N14', 1.1703e-03) +mat.add_nuclide('H1', 6.3783e-02) +mat.add_nuclide('O16', 3.5288e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-10/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/geometry.xml new file mode 100644 index 0000000..52ba714 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-10/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/materials.xml new file mode 100644 index 0000000..7252de3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-10/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-10/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..6f7b185 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.5214e-08) +mat.add_nuclide('Pu239', 5.5529e-04) +mat.add_nuclide('Pu240', 2.7168e-05) +mat.add_nuclide('Pu241', 1.7677e-06) +mat.add_nuclide('Pu242', 5.1947e-08) +mat.add_nuclide('N14', 2.6320e-03) +mat.add_nuclide('H1', 6.0833e-02) +mat.add_nuclide('O16', 3.8165e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/geometry.xml new file mode 100644 index 0000000..30e05a1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/materials.xml new file mode 100644 index 0000000..787560c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..6bb7a4b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.3545e-08) +mat.add_nuclide('Pu239', 5.2896e-04) +mat.add_nuclide('Pu240', 2.5880e-05) +mat.add_nuclide('Pu241', 1.6839e-06) +mat.add_nuclide('Pu242', 4.9484e-08) +mat.add_nuclide('N14', 2.6058e-03) +mat.add_nuclide('H1', 6.0287e-02) +mat.add_nuclide('O16', 3.7771e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/geometry.xml new file mode 100644 index 0000000..b773f90 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/materials.xml new file mode 100644 index 0000000..190be5c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..42b4d24 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.5209e-08) +mat.add_nuclide('Pu239', 2.3983e-04) +mat.add_nuclide('Pu240', 1.1734e-05) +mat.add_nuclide('Pu241', 7.6348e-07) +mat.add_nuclide('Pu242', 2.2436e-08) +mat.add_nuclide('N14', 1.1898e-03) +mat.add_nuclide('H1', 6.4161e-02) +mat.add_nuclide('O16', 3.5560e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/geometry.xml new file mode 100644 index 0000000..ae2d257 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/materials.xml new file mode 100644 index 0000000..5630c64 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..9bf69b7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.5406e-08) +mat.add_nuclide('Pu239', 2.4294e-04) +mat.add_nuclide('Pu240', 1.1886e-05) +mat.add_nuclide('Pu241', 7.7338e-07) +mat.add_nuclide('Pu242', 2.2727e-08) +mat.add_nuclide('N14', 1.2577e-03) +mat.add_nuclide('H1', 6.3655e-02) +mat.add_nuclide('O16', 3.5483e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/geometry.xml new file mode 100644 index 0000000..6d5093e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/materials.xml new file mode 100644 index 0000000..8250081 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..0b88743 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.5194e-08) +mat.add_nuclide('Pu239', 2.3959e-04) +mat.add_nuclide('Pu240', 1.1722e-05) +mat.add_nuclide('Pu241', 7.6272e-07) +mat.add_nuclide('Pu242', 2.2413e-08) +mat.add_nuclide('N14', 1.2616e-03) +mat.add_nuclide('H1', 6.3671e-02) +mat.add_nuclide('O16', 3.5494e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/geometry.xml new file mode 100644 index 0000000..06d2d91 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/materials.xml new file mode 100644 index 0000000..230bb01 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..8176f0a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.5421e-08) +mat.add_nuclide('Pu239', 2.4318e-04) +mat.add_nuclide('Pu240', 1.1898e-05) +mat.add_nuclide('Pu241', 7.7414e-07) +mat.add_nuclide('Pu242', 2.2749e-08) +mat.add_nuclide('N14', 1.3791e-03) +mat.add_nuclide('H1', 6.2853e-02) +mat.add_nuclide('O16', 3.5386e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/geometry.xml new file mode 100644 index 0000000..48f7ec6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/materials.xml new file mode 100644 index 0000000..ea40e7a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-9/generate_materials.py b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..a8a9445 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.5421e-08) +mat.add_nuclide('Pu239', 2.4318e-04) +mat.add_nuclide('Pu240', 1.1898e-05) +mat.add_nuclide('Pu241', 7.7414e-07) +mat.add_nuclide('Pu242', 2.2749e-08) +mat.add_nuclide('N14', 1.3850e-03) +mat.add_nuclide('H1', 6.3152e-02) +mat.add_nuclide('O16', 3.5550e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 25 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6655e-02) +mat.add_nuclide('O16', 3.3327e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-9/geometry.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/geometry.xml new file mode 100644 index 0000000..bedcb4a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/geometry.xml @@ -0,0 +1,23 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-9/materials.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/materials.xml new file mode 100644 index 0000000..dbb5324 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/materials.xml @@ -0,0 +1,38 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-007/openmc/case-9/settings.xml b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/settings.xml new file mode 100644 index 0000000..9f15518 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-007/openmc/case-9/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-1.py b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-1.py new file mode 100644 index 0000000..9c2f8c8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-1.py @@ -0,0 +1,125 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.0139e-09], + ['Pu239',2.4582e-05], + ['Pu240',6.3369e-07], + ['Pu242',3.4900000000000006e-09], + ['N14',0.00077494], + ['H1',0.065098], + ['O16',0.034542], + ['Al27',2.111e-06], + ['B10',1.461725e-09], + ['B11',5.913275e-09], + ['Cd106',4.4160149999999995e-12], + ['Cd108',3.1497360000000004e-12], + ['Cd110',4.423109e-11], + ['Cd111',4.5383865e-11], + ['Cd112',8.5514623e-11], + ['Cd113',4.3369169e-11], + ['Cd114',1.0199043800000001e-10], + ['Cd116',2.6645063999999997e-11], + ['Cl35',2.4335621639999998e-08], + ['Cl37',7.784378360000001e-09], + ['Ca40',4.13259483e-08], + ['Ca42',2.758161e-10], + ['Ca43',5.75505e-11], + ['Ca44',8.892618e-10], + ['Ca46',1.7051999999999998e-12], + ['Ca48',7.97181e-11], + ['Cr50',7.138835000000001e-09], + ['Cr52',1.37665327e-07], + ['Cr53',1.5610143e-08], + ['Cr54',3.885695e-09], + ['Gd152',7.244e-13], + ['Gd154',7.89596e-12], + ['Gd155',5.3605599999999996e-11], + ['Gd156',7.414234e-11], + ['Gd157',5.66843e-11], + ['Gd158',8.997048e-11], + ['Gd160',7.917692e-11], + ['Ga69',2.4554117999999995e-07], + ['Ga71',1.6295882e-07], + ['Fe54',4.172161e-08], + ['Fe56',6.549400520000001e-07], + ['Fe57',1.5125422e-08], + ['Fe58',2.012916e-09], + ['F19',2.998e-07], + ['Mg24',3.69885435e-08], + ['Mg25',4.69437e-09], + ['Mg26',5.1670864999999995e-09], + ['Mn55',1.555e-08], + ['Ni58',6.606182376e-08], + ['Ni60',2.5446896239999996e-08], + ['Ni61',1.10615896e-09], + ['Ni62',3.5269187999999997e-09], + ['Ni64',8.982022400000001e-10], + ['P31',1.839e-07], + ['K39',1.358770517e-08], + ['K40',1.70469e-12], + ['K41',9.8059014e-10], + ['S32',1.6879235424000002e-07], + ['S33',1.32967344e-09], + ['S34',7.45207824e-09], + ['S36',2.589408e-11], + ['Si28',9.352089552e-08], + ['Si29',4.74872424e-09], + ['Si30',3.13038024e-09], + ['Na23',7.431e-08], + ['U235',7.2690000000000004e-09]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.964, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.734, bc='vacuum') +s3 = mcdc.surface('plane-z', z=15.9564, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(-s1 & +s3, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-1a.py b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-1a.py new file mode 100644 index 0000000..ba7bae4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-1a.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.0139e-09], + ['Pu239',2.4581999999999996e-05], + ['Pu240',6.3369e-07], + ['Pu242',3.4899999999999997e-09], + ['N14',0.00076339], + ['H1',0.065198], + ['O16',0.034558]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.964, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.734, bc='vacuum') +s3 = mcdc.surface('plane-z', z=15.9564, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(-s1 & +s3, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-2.py b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-2.py new file mode 100644 index 0000000..c4bebad --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-2.py @@ -0,0 +1,125 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',9.6526e-10], + ['Pu239',2.3402e-05], + ['Pu240',6.0327e-07], + ['Pu242',3.3224e-09], + ['N14',0.00076951], + ['H1',0.065031], + ['O16',0.034493], + ['Al27',2.111e-06], + ['B10',1.461725e-09], + ['B11',5.913275e-09], + ['Cd106',4.4160149999999995e-12], + ['Cd108',3.1497359999999996e-12], + ['Cd110',4.423109e-11], + ['Cd111',4.5383865e-11], + ['Cd112',8.5514623e-11], + ['Cd113',4.3369169e-11], + ['Cd114',1.0199043799999998e-10], + ['Cd116',2.6645064e-11], + ['Cl35',2.4335621639999998e-08], + ['Cl37',7.784378360000001e-09], + ['Ca40',4.13259483e-08], + ['Ca42',2.758161e-10], + ['Ca43',5.75505e-11], + ['Ca44',8.892617999999998e-10], + ['Ca46',1.7051999999999998e-12], + ['Ca48',7.97181e-11], + ['Cr50',7.138835000000001e-09], + ['Cr52',1.37665327e-07], + ['Cr53',1.5610143e-08], + ['Cr54',3.885695e-09], + ['Gd152',7.244e-13], + ['Gd154',7.89596e-12], + ['Gd155',5.36056e-11], + ['Gd156',7.414234e-11], + ['Gd157',5.668429999999999e-11], + ['Gd158',8.997048e-11], + ['Gd160',7.917692e-11], + ['Ga69',2.4554117999999995e-07], + ['Ga71',1.6295882e-07], + ['Fe54',4.172161e-08], + ['Fe56',6.549400520000001e-07], + ['Fe57',1.5125422e-08], + ['Fe58',2.012916e-09], + ['F19',2.998e-07], + ['Mg24',3.69885435e-08], + ['Mg25',4.69437e-09], + ['Mg26',5.1670864999999995e-09], + ['Mn55',1.555e-08], + ['Ni58',6.606182376e-08], + ['Ni60',2.544689624e-08], + ['Ni61',1.10615896e-09], + ['Ni62',3.5269188e-09], + ['Ni64',8.982022399999999e-10], + ['P31',1.839e-07], + ['K39',1.358770517e-08], + ['K40',1.7046900000000003e-12], + ['K41',9.8059014e-10], + ['S32',1.6879235424000002e-07], + ['S33',1.32967344e-09], + ['S34',7.45207824e-09], + ['S36',2.589408e-11], + ['Si28',9.352089552e-08], + ['Si29',4.74872424e-09], + ['Si30',3.13038024e-09], + ['Na23',7.431e-08], + ['U235',7.269e-09]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.964, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.734, bc='vacuum') +s3 = mcdc.surface('plane-z', z=45.3717, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(-s1 & +s3, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-2a.py b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-2a.py new file mode 100644 index 0000000..92a9503 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-2a.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',9.6526e-10], + ['Pu239',2.3402e-05], + ['Pu240',6.0327e-07], + ['Pu242',3.3224e-09], + ['N14',0.00075853], + ['H1',0.065131], + ['O16',0.03451]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.964, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.734, bc='vacuum') +s3 = mcdc.surface('plane-z', z=45.3717, bc='interface') + +# Material Cell(s) +c1 = mcdc.cell(-s1 & -s3, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(-s1 & +s3, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-3.py b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-3.py new file mode 100644 index 0000000..6d86569 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-3.py @@ -0,0 +1,123 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',9.7592e-10], + ['Pu239',2.3201e-05], + ['Pu240',5.9809e-07], + ['Pu242',3.2939000000000004e-09], + ['N14',0.00077164], + ['H1',0.065027], + ['O16',0.034496], + ['Al27',2.111e-06], + ['B10',1.461725e-09], + ['B11',5.913275e-09], + ['Cd106',4.4160149999999995e-12], + ['Cd108',3.149736e-12], + ['Cd110',4.423109e-11], + ['Cd111',4.5383865e-11], + ['Cd112',8.5514623e-11], + ['Cd113',4.3369169e-11], + ['Cd114',1.0199043799999998e-10], + ['Cd116',2.6645064e-11], + ['Cl35',2.433562164e-08], + ['Cl37',7.784378360000001e-09], + ['Ca40',4.13259483e-08], + ['Ca42',2.758161e-10], + ['Ca43',5.75505e-11], + ['Ca44',8.892617999999999e-10], + ['Ca46',1.7052e-12], + ['Ca48',7.97181e-11], + ['Cr50',7.1388350000000014e-09], + ['Cr52',1.37665327e-07], + ['Cr53',1.5610143e-08], + ['Cr54',3.885695e-09], + ['Gd152',7.244e-13], + ['Gd154',7.89596e-12], + ['Gd155',5.3605599999999996e-11], + ['Gd156',7.414234e-11], + ['Gd157',5.6684300000000006e-11], + ['Gd158',8.997048e-11], + ['Gd160',7.917692e-11], + ['Ga69',2.4554117999999995e-07], + ['Ga71',1.6295882e-07], + ['Fe54',4.172161e-08], + ['Fe56',6.549400520000001e-07], + ['Fe57',1.5125422e-08], + ['Fe58',2.012916e-09], + ['F19',2.998e-07], + ['Mg24',3.69885435e-08], + ['Mg25',4.69437e-09], + ['Mg26',5.1670864999999995e-09], + ['Mn55',1.555e-08], + ['Ni58',6.606182376e-08], + ['Ni60',2.5446896240000002e-08], + ['Ni61',1.10615896e-09], + ['Ni62',3.5269187999999997e-09], + ['Ni64',8.9820224e-10], + ['P31',1.839e-07], + ['K39',1.3587705169999998e-08], + ['K40',1.70469e-12], + ['K41',9.8059014e-10], + ['S32',1.6879235424000002e-07], + ['S33',1.32967344e-09], + ['S34',7.45207824e-09], + ['S36',2.589408e-11], + ['Si28',9.352089552e-08], + ['Si29',4.74872424e-09], + ['Si30',3.13038024e-09], + ['Na23',7.431e-08], + ['U235',7.2690000000000004e-09]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.964, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.734, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-3a.py b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-3a.py new file mode 100644 index 0000000..655e836 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/mcdc/pu-sol-therm-009_case-3a.py @@ -0,0 +1,64 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',9.7592e-10], + ['Pu239',2.3201e-05], + ['Pu240',5.9809e-07], + ['Pu242',3.2939e-09], + ['N14',0.00076076], + ['H1',0.065121], + ['O16',0.03451]]) +# Material Name: 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00034835150136], + ['Si29',1.7688295320000002e-05], + ['Si30',1.166020332e-05], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Zn64',1.2271848600000001e-05], + ['Zn66',6.9208534e-06], + ['Zn67',1.0083032e-06], + ['Zn68',4.604751e-06], + ['Zn70',1.522438e-07], + ['Mn55',1.4853000000000002e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=60.964, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.734, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..5db83c4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/generate_materials.py @@ -0,0 +1,48 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.0139e-09) +mat.add_nuclide('Pu239', 2.4582e-05) +mat.add_nuclide('Pu240', 6.3369e-07) +mat.add_nuclide('Pu241', 1.8774e-08) +mat.add_nuclide('Pu242', 3.4900e-09) +mat.add_nuclide('N14', 7.7494e-04) +mat.add_nuclide('H1', 6.5098e-02) +mat.add_nuclide('O16', 3.4542e-02) +mat.add_element('Al', 2.1110e-06) +mat.add_element('B', 7.3750e-09) +mat.add_element('Cd', 3.5470e-10) +mat.add_element('Cl', 3.2120e-08) +mat.add_element('Ca', 4.2630e-08) +mat.add_element('Cr', 1.6430e-07) +mat.add_element('Gd', 3.6220e-10) +mat.add_element('Ga', 4.0850e-07) +mat.add_element('Fe', 7.1380e-07) +mat.add_element('F', 2.9980e-07) +mat.add_element('Mg', 4.6850e-08) +mat.add_element('Mn', 1.5550e-08) +mat.add_element('Ni', 9.7040e-08) +mat.add_element('P', 1.8390e-07) +mat.add_element('K', 1.4570e-08) +mat.add_element('S', 1.7760e-07) +mat.add_element('Si', 1.0140e-07) +mat.add_element('Na', 7.4310e-08) +mat.add_nuclide('U235', 7.2690e-09) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/geometry.xml new file mode 100644 index 0000000..131248a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/materials.xml new file mode 100644 index 0000000..5151f4d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/materials.xml @@ -0,0 +1,89 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/generate_materials.py b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/generate_materials.py new file mode 100644 index 0000000..db504ca --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.0139e-09) +mat.add_nuclide('Pu239', 2.4582e-05) +mat.add_nuclide('Pu240', 6.3369e-07) +mat.add_nuclide('Pu241', 1.8774e-08) +mat.add_nuclide('Pu242', 3.4900e-09) +mat.add_nuclide('N14', 7.6339e-04) +mat.add_nuclide('H1', 6.5198e-02) +mat.add_nuclide('O16', 3.4558e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/geometry.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/geometry.xml new file mode 100644 index 0000000..b242ade --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/materials.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/materials.xml new file mode 100644 index 0000000..aead72d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/settings.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-1a/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..8e2e966 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/generate_materials.py @@ -0,0 +1,48 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 9.6526e-10) +mat.add_nuclide('Pu239', 2.3402e-05) +mat.add_nuclide('Pu240', 6.0327e-07) +mat.add_nuclide('Pu241', 1.7873e-08) +mat.add_nuclide('Pu242', 3.3224e-09) +mat.add_nuclide('N14', 7.6951e-04) +mat.add_nuclide('H1', 6.5031e-02) +mat.add_nuclide('O16', 3.4493e-02) +mat.add_element('Al', 2.1110e-06) +mat.add_element('B', 7.3750e-09) +mat.add_element('Cd', 3.5470e-10) +mat.add_element('Cl', 3.2120e-08) +mat.add_element('Ca', 4.2630e-08) +mat.add_element('Cr', 1.6430e-07) +mat.add_element('Gd', 3.6220e-10) +mat.add_element('Ga', 4.0850e-07) +mat.add_element('Fe', 7.1380e-07) +mat.add_element('F', 2.9980e-07) +mat.add_element('Mg', 4.6850e-08) +mat.add_element('Mn', 1.5550e-08) +mat.add_element('Ni', 9.7040e-08) +mat.add_element('P', 1.8390e-07) +mat.add_element('K', 1.4570e-08) +mat.add_element('S', 1.7760e-07) +mat.add_element('Si', 1.0140e-07) +mat.add_element('Na', 7.4310e-08) +mat.add_nuclide('U235', 7.2690e-09) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/geometry.xml new file mode 100644 index 0000000..88c3484 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/materials.xml new file mode 100644 index 0000000..c4660ae --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/materials.xml @@ -0,0 +1,89 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/generate_materials.py b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/generate_materials.py new file mode 100644 index 0000000..7312df5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 9.6526e-10) +mat.add_nuclide('Pu239', 2.3402e-05) +mat.add_nuclide('Pu240', 6.0327e-07) +mat.add_nuclide('Pu241', 1.7873e-08) +mat.add_nuclide('Pu242', 3.3224e-09) +mat.add_nuclide('N14', 7.5853e-04) +mat.add_nuclide('H1', 6.5131e-02) +mat.add_nuclide('O16', 3.4510e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/geometry.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/geometry.xml new file mode 100644 index 0000000..05b2369 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/materials.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/materials.xml new file mode 100644 index 0000000..5c5c44d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/settings.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-2a/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..d9d83b3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/generate_materials.py @@ -0,0 +1,48 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 9.7592e-10) +mat.add_nuclide('Pu239', 2.3201e-05) +mat.add_nuclide('Pu240', 5.9809e-07) +mat.add_nuclide('Pu241', 1.7720e-08) +mat.add_nuclide('Pu242', 3.2939e-09) +mat.add_nuclide('N14', 7.7164e-04) +mat.add_nuclide('H1', 6.5027e-02) +mat.add_nuclide('O16', 3.4496e-02) +mat.add_element('Al', 2.1110e-06) +mat.add_element('B', 7.3750e-09) +mat.add_element('Cd', 3.5470e-10) +mat.add_element('Cl', 3.2120e-08) +mat.add_element('Ca', 4.2630e-08) +mat.add_element('Cr', 1.6430e-07) +mat.add_element('Gd', 3.6220e-10) +mat.add_element('Ga', 4.0850e-07) +mat.add_element('Fe', 7.1380e-07) +mat.add_element('F', 2.9980e-07) +mat.add_element('Mg', 4.6850e-08) +mat.add_element('Mn', 1.5550e-08) +mat.add_element('Ni', 9.7040e-08) +mat.add_element('P', 1.8390e-07) +mat.add_element('K', 1.4570e-08) +mat.add_element('S', 1.7760e-07) +mat.add_element('Si', 1.0140e-07) +mat.add_element('Na', 7.4310e-08) +mat.add_nuclide('U235', 7.2690e-09) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/geometry.xml new file mode 100644 index 0000000..5604ff6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/materials.xml new file mode 100644 index 0000000..e90598f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/materials.xml @@ -0,0 +1,89 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/generate_materials.py b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/generate_materials.py new file mode 100644 index 0000000..6681acf --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 9.7592e-10) +mat.add_nuclide('Pu239', 2.3201e-05) +mat.add_nuclide('Pu240', 5.9809e-07) +mat.add_nuclide('Pu241', 1.7720e-08) +mat.add_nuclide('Pu242', 3.2939e-09) +mat.add_nuclide('N14', 7.6076e-04) +mat.add_nuclide('H1', 6.5121e-02) +mat.add_nuclide('O16', 3.4510e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 3.7770e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Zn', 2.4958e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/geometry.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/geometry.xml new file mode 100644 index 0000000..9d5ca44 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/materials.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/materials.xml new file mode 100644 index 0000000..2ef35fb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/settings.xml b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-009/openmc/case-3a/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-1.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-1.py new file mode 100644 index 0000000..e4cec61 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-1.py @@ -0,0 +1,67 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.4397e-05], + ['Pu240',3.6572e-06], + ['N14',0.001014], + ['H1',0.064544], + ['O16',0.034983], + ['Fe54',6.5551675e-08], + ['Fe56',1.02902111e-06], + ['Fe57',2.3764585e-08], + ['Fe58',3.16263e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.1206, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.2476, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-2.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-2.py new file mode 100644 index 0000000..ae60215 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-2.py @@ -0,0 +1,67 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',8.7439e-05], + ['Pu240',3.7889999999999996e-06], + ['N14',0.0010625], + ['H1',0.064357], + ['O16',0.035017], + ['Fe54',7.56343e-08], + ['Fe56',1.18729676e-06], + ['Fe57',2.7419860000000002e-08], + ['Fe58',3.6490800000000004e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.1206, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.2476, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-3.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-3.py new file mode 100644 index 0000000..e3ab1a1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-3.py @@ -0,0 +1,67 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.205e-05], + ['Pu240',3.9888e-06], + ['N14',0.0015830999999999998], + ['H1',0.063652], + ['O16',0.035976], + ['Fe54',7.815349500000001e-08], + ['Fe56',1.226842734e-06], + ['Fe57',2.8333149000000004e-08], + ['Fe58',3.770622000000001e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.1206, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.2476, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-4.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-4.py new file mode 100644 index 0000000..b31dab8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-4.py @@ -0,0 +1,67 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.2122e-05], + ['Pu240',3.9919e-06], + ['N14',0.0017481999999999999], + ['H1',0.062803], + ['O16',0.035964], + ['Fe54',1.1218893000000002e-07], + ['Fe56',1.7611262760000002e-06], + ['Fe57',4.0672086e-08], + ['Fe58',5.412708000000001e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.1206, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.2476, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-5.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-5.py new file mode 100644 index 0000000..f569396 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-16-5.py @@ -0,0 +1,67 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.00010484], + ['Pu240',4.5432e-06], + ['N14',0.0027369], + ['H1',0.06023300000000001], + ['O16',0.037177], + ['Fe54',1.1282019000000001e-07], + ['Fe56',1.7710357080000002e-06], + ['Fe57',4.0900938000000004e-08], + ['Fe58',5.4431640000000005e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.1206, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=20.2476, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-1.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-1.py new file mode 100644 index 0000000..e14264c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-1.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.3938e-05], + ['Pu240',2.3549e-06], + ['N14',0.0007393], + ['H1',0.065147], + ['O16',0.034534], + ['Fe54',7.56343e-08], + ['Fe56',1.18729676e-06], + ['Fe57',2.7419860000000002e-08], + ['Fe58',3.64908e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-2.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-2.py new file mode 100644 index 0000000..1cd041f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-2.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.6158999999999995e-05], + ['Pu240',2.4518e-06], + ['N14',0.0009495699999999998], + ['H1',0.064659], + ['O16',0.03482], + ['Fe54',7.9416015e-08], + ['Fe56',1.246661598e-06], + ['Fe57',2.8790853000000002e-08], + ['Fe58',3.831534e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-3.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-3.py new file mode 100644 index 0000000..fc0bef2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-3.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.574800000000001e-05], + ['Pu240',2.4339e-06], + ['N14',0.0010468], + ['H1',0.064569], + ['O16',0.035018], + ['Fe54',8.508566500000001e-08], + ['Fe56',1.3356629780000001e-06], + ['Fe57',3.0846283000000005e-08], + ['Fe58',4.105074000000001e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-4.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-4.py new file mode 100644 index 0000000..ed7ec9a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-4.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.748599999999999e-05], + ['Pu240',2.5097e-06], + ['N14',0.0014414], + ['H1',0.06322], + ['O16',0.035333], + ['Fe54',7.7522235e-08], + ['Fe56',1.216933302e-06], + ['Fe57',2.8104297e-08], + ['Fe58',3.740166e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-5.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-5.py new file mode 100644 index 0000000..304d3ed --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-5.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.0816e-05], + ['Pu240',2.6552e-06], + ['N14',0.0019343], + ['H1',0.06318], + ['O16',0.036553], + ['Fe54',8.634818500000001e-08], + ['Fe56',1.355481842e-06], + ['Fe57',3.1303987e-08], + ['Fe58',4.165986e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-6.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-6.py new file mode 100644 index 0000000..ce016dd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-6.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',6.6343e-05], + ['Pu240',2.8964e-06], + ['N14',0.0027753], + ['H1',0.060264000000000005], + ['O16',0.037209], + ['Fe54',8.886738000000001e-08], + ['Fe56',1.395027816e-06], + ['Fe57',3.2217276000000005e-08], + ['Fe58',4.287528e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-7.py b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-7.py new file mode 100644 index 0000000..97e3840 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/mcdc/pu-sol-therm-011_case-18-7.py @@ -0,0 +1,79 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.7776e-05], + ['Pu240',2.5224e-06], + ['N14',0.0012199], + ['H1',0.063701], + ['O16',0.035021], + ['Fe54',2.4518021499999997e-08], + ['Fe56',3.8488050380000003e-07], + ['Fe57',8.8885693e-09], + ['Fe58',1.1829054e-09]]) +# Material Name: 347 Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035295617000000003], + ['Fe56',0.055406570440000004], + ['Fe57',0.00127957934], + ['Fe58',0.00017028851999999998], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0067058469576], + ['Ni60',0.0025830802424], + ['Ni61',0.0001122847096], + ['Ni62',0.000358012788], + ['Ni64',9.117530240000001e-05]]) +# Material Name: Cadmium +m3 = mcdc.material(nuclides=[ + ['Cd106',0.000576933], + ['Cd108',0.0004114992], + ['Cd110',0.005778598], + ['Cd111',0.005929203], + ['Cd112',0.0111721106], + ['Cd113',0.0056659918], + ['Cd114',0.0133246036], + ['Cd116',0.0034810608]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.6974, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8244, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=22.8752, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/generate_materials.py new file mode 100644 index 0000000..072fb78 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/generate_materials.py @@ -0,0 +1,25 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.4397e-05) +mat.add_nuclide('Pu240', 3.6572e-06) +mat.add_nuclide('N14', 1.0140e-03) +mat.add_nuclide('H1', 6.4544e-02) +mat.add_nuclide('O16', 3.4983e-02) +mat.add_element('Fe', 1.1215e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/geometry.xml new file mode 100644 index 0000000..6779537 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/materials.xml new file mode 100644 index 0000000..f814a1d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/generate_materials.py new file mode 100644 index 0000000..a2c9ec8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/generate_materials.py @@ -0,0 +1,25 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 8.7439e-05) +mat.add_nuclide('Pu240', 3.7890e-06) +mat.add_nuclide('N14', 1.0625e-03) +mat.add_nuclide('H1', 6.4357e-02) +mat.add_nuclide('O16', 3.5017e-02) +mat.add_element('Fe', 1.2940e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/geometry.xml new file mode 100644 index 0000000..4ee5c5f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/materials.xml new file mode 100644 index 0000000..cc2b41d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/generate_materials.py new file mode 100644 index 0000000..9690156 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/generate_materials.py @@ -0,0 +1,25 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.2050e-05) +mat.add_nuclide('Pu240', 3.9888e-06) +mat.add_nuclide('N14', 1.5831e-03) +mat.add_nuclide('H1', 6.3652e-02) +mat.add_nuclide('O16', 3.5976e-02) +mat.add_element('Fe', 1.3371e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/geometry.xml new file mode 100644 index 0000000..a6c4216 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/materials.xml new file mode 100644 index 0000000..8492744 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/generate_materials.py new file mode 100644 index 0000000..9c3bead --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/generate_materials.py @@ -0,0 +1,25 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.2122e-05) +mat.add_nuclide('Pu240', 3.9919e-06) +mat.add_nuclide('N14', 1.7482e-03) +mat.add_nuclide('H1', 6.2803e-02) +mat.add_nuclide('O16', 3.5964e-02) +mat.add_element('Fe', 1.9194e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/geometry.xml new file mode 100644 index 0000000..1c142d0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/materials.xml new file mode 100644 index 0000000..be8f451 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/generate_materials.py new file mode 100644 index 0000000..8428d2e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/generate_materials.py @@ -0,0 +1,25 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.0484e-04) +mat.add_nuclide('Pu240', 4.5432e-06) +mat.add_nuclide('N14', 2.7369e-03) +mat.add_nuclide('H1', 6.0233e-02) +mat.add_nuclide('O16', 3.7177e-02) +mat.add_element('Fe', 1.9302e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/geometry.xml new file mode 100644 index 0000000..943630a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/materials.xml new file mode 100644 index 0000000..fdd59c0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-16-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/generate_materials.py new file mode 100644 index 0000000..2564f14 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.3938e-05) +mat.add_nuclide('Pu240', 2.3549e-06) +mat.add_nuclide('N14', 7.3930e-04) +mat.add_nuclide('H1', 6.5147e-02) +mat.add_nuclide('O16', 3.4534e-02) +mat.add_element('Fe', 1.2940e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/geometry.xml new file mode 100644 index 0000000..7f5f509 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/materials.xml new file mode 100644 index 0000000..a4284df --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/generate_materials.py new file mode 100644 index 0000000..11ba4ae --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.6159e-05) +mat.add_nuclide('Pu240', 2.4518e-06) +mat.add_nuclide('N14', 9.4957e-04) +mat.add_nuclide('H1', 6.4659e-02) +mat.add_nuclide('O16', 3.4820e-02) +mat.add_element('Fe', 1.3587e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/geometry.xml new file mode 100644 index 0000000..e4acec3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/materials.xml new file mode 100644 index 0000000..117ba52 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/generate_materials.py new file mode 100644 index 0000000..86652e6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.5748e-05) +mat.add_nuclide('Pu240', 2.4339e-06) +mat.add_nuclide('N14', 1.0468e-03) +mat.add_nuclide('H1', 6.4569e-02) +mat.add_nuclide('O16', 3.5018e-02) +mat.add_element('Fe', 1.4557e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/geometry.xml new file mode 100644 index 0000000..c662743 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/materials.xml new file mode 100644 index 0000000..9ea1580 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/generate_materials.py new file mode 100644 index 0000000..7f8f8bc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.7486e-05) +mat.add_nuclide('Pu240', 2.5097e-06) +mat.add_nuclide('N14', 1.4414e-03) +mat.add_nuclide('H1', 6.3220e-02) +mat.add_nuclide('O16', 3.5333e-02) +mat.add_element('Fe', 1.3263e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/geometry.xml new file mode 100644 index 0000000..edbf8ea --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/materials.xml new file mode 100644 index 0000000..4ec38b5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/generate_materials.py new file mode 100644 index 0000000..30c7895 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.0816e-05) +mat.add_nuclide('Pu240', 2.6552e-06) +mat.add_nuclide('N14', 1.9343e-03) +mat.add_nuclide('H1', 6.3180e-02) +mat.add_nuclide('O16', 3.6553e-02) +mat.add_element('Fe', 1.4773e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/geometry.xml new file mode 100644 index 0000000..89dc5ce --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/materials.xml new file mode 100644 index 0000000..31cc92b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/generate_materials.py new file mode 100644 index 0000000..6334fd9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 6.6343e-05) +mat.add_nuclide('Pu240', 2.8964e-06) +mat.add_nuclide('N14', 2.7753e-03) +mat.add_nuclide('H1', 6.0264e-02) +mat.add_nuclide('O16', 3.7209e-02) +mat.add_element('Fe', 1.5204e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/geometry.xml new file mode 100644 index 0000000..727a9e7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/materials.xml new file mode 100644 index 0000000..c3822f1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/generate_materials.py new file mode 100644 index 0000000..61d53e5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.7776e-05) +mat.add_nuclide('Pu240', 2.5224e-06) +mat.add_nuclide('N14', 1.2199e-03) +mat.add_nuclide('H1', 6.3701e-02) +mat.add_nuclide('O16', 3.5021e-02) +mat.add_element('Fe', 4.1947e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "347 Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 6.0386e-02) +mat.add_element('Cr', 1.6678e-02) +mat.add_element('Ni', 9.8504e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Cadmium" +mat.set_density('sum') +mat.add_element('Cd', 4.6340e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/geometry.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/geometry.xml new file mode 100644 index 0000000..99ca925 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/materials.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/materials.xml new file mode 100644 index 0000000..5e772b6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/materials.xml @@ -0,0 +1,43 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/settings.xml b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-011/openmc/case-18-7/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-1.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-1.py new file mode 100644 index 0000000..82e523e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-1.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (19.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.68825e-05], + ['Pu240',9.34548e-06], + ['Pu242',5.59608e-07], + ['Am241',3.0021e-07], + ['N14',0.00140826256928], + ['N15',5.17743072e-06], + ['O16',0.0353798859393], + ['O17',1.3414060700000003e-05], + ['H1',0.0634983], + ['Fe54',2.89928366e-07], + ['Fe56',4.5512553112e-06], + ['Fe57',1.0510833319999998e-07], + ['Fe58',1.39879896e-08], + ['Cr50',6.93075295e-08], + ['Cr52',1.3365267179000001e-06], + ['Cr53',1.515514011e-07], + ['Cr54',3.7724351500000005e-08], + ['Ni58',7.696365852600001e-07], + ['Ni60',2.9646263474000003e-07], + ['Ni61',1.288702546e-08], + ['Ni62',4.10894763e-08], + ['Ni64',1.046427824e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=28.17, bc='interface') +s25 = mcdc.surface('plane-z', z=29.17, bc='interface') +s26 = mcdc.surface('plane-z', z=47.17, bc='interface') +s27 = mcdc.surface('plane-z', z=48.17, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s25 & -s26, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s25 & -s26, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s25 & -s26, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s25 & -s26, fill=m5) +c27 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s27, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s27, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s27, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s27, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s27 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s27 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s27 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-10.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-10.py new file mode 100644 index 0000000..eb43316 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-10.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (26.9 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.03642e-05], + ['Pu240',1.27611e-05], + ['Pu242',7.641340000000001e-07], + ['Am241',4.09931e-07], + ['N14',0.0015229409579800002], + ['N15',5.5990420200000005e-06], + ['O16',0.0354792482667], + ['O17',1.34517333e-05], + ['H1',0.0630426], + ['Fe54',3.718641605e-07], + ['Fe56',5.8374720586e-06], + ['Fe57',1.348126871e-07], + ['Fe58',1.79410938e-08], + ['Cr50',8.889435500000002e-08], + ['Cr52',1.714239151e-06], + ['Cr53',1.9438095900000004e-07], + ['Cr54',4.838553500000001e-08], + ['Ni58',9.8714228076e-07], + ['Ni60',3.8024543923999996e-07], + ['Ni61',1.6529005959999998e-08], + ['Ni62',5.27017038e-08], + ['Ni64',1.3421570239999999e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=23.11, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-11.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-11.py new file mode 100644 index 0000000..1a111a5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-11.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (21.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',4.0627e-05], + ['Pu240',1.02943e-05], + ['Pu242',6.1642e-07], + ['Am241',3.30688e-07], + ['N14',0.00141229773413], + ['N15',5.19226587e-06], + ['O16',0.0354768491763], + ['O17',1.34508237e-05], + ['H1',0.06365], + ['Fe54',3.151396045e-07], + ['Fe56',4.9470178394000006e-06], + ['Fe57',1.1424821590000001e-07], + ['Fe58',1.52043402e-08], + ['Cr50',7.533404450000001e-08], + ['Cr52',1.4527420609e-06], + ['Cr53',1.647292881e-07], + ['Cr54',4.1004606500000004e-08], + ['Ni58',8.3656298565e-07], + ['Ni60',3.2224256435000004e-07], + ['Ni61',1.400766115e-08], + ['Ni62',4.466255325000001e-08], + ['Ni64',1.1374235600000002e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=27.15, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-12.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-12.py new file mode 100644 index 0000000..6d361ff --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-12.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (19.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.68825e-05], + ['Pu240',9.34548e-06], + ['Pu242',5.59608e-07], + ['Am241',3.0021e-07], + ['N14',0.00140826256928], + ['N15',5.17743072e-06], + ['O16',0.0353798859393], + ['O17',1.3414060700000003e-05], + ['H1',0.0634983], + ['Fe54',2.89928366e-07], + ['Fe56',4.5512553112e-06], + ['Fe57',1.0510833319999998e-07], + ['Fe58',1.39879896e-08], + ['Cr50',6.93075295e-08], + ['Cr52',1.3365267179000001e-06], + ['Cr53',1.515514011e-07], + ['Cr54',3.7724351500000005e-08], + ['Ni58',7.696365852600001e-07], + ['Ni60',2.9646263474000003e-07], + ['Ni61',1.288702546e-08], + ['Ni62',4.10894763e-08], + ['Ni64',1.046427824e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=29.9, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-13.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-13.py new file mode 100644 index 0000000..570d25d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-13.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (13.2 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',2.47132e-05], + ['Pu240',6.26195e-06], + ['Pu242',3.74965e-07], + ['Am241',2.01156e-07], + ['N14',0.0013666256460500002], + ['N15',5.024353950000001e-06], + ['O16',0.035287720883100004], + ['O17',1.3379116900000002e-05], + ['H1',0.0635948], + ['Fe54',2.07991987e-07], + ['Fe56',3.2650293884000003e-06], + ['Fe57',7.54037674e-08], + ['Fe58',1.0034857200000001e-08], + ['Cr50',4.972026950000001e-08], + ['Cr52',9.588059059e-07], + ['Cr53',1.087208931e-07], + ['Cr54',2.7062931500000002e-08], + ['Ni58',5.52129528222e-07], + ['Ni60',2.1267930577800002e-07], + ['Ni61',9.245022161999999e-09], + ['Ni62',2.9477176110000006e-08], + ['Ni64',7.506967728000001e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=67.46, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,67.46], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-14.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-14.py new file mode 100644 index 0000000..76ff641 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-14.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (52.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.86655e-05], + ['Pu240',2.5000399999999995e-05], + ['Pu242',1.49702e-06], + ['Am241',8.03099e-07], + ['N14',0.0017784316548899999], + ['N15',6.538345109999999e-06], + ['O16',0.0359427725244], + ['O17',1.36274756e-05], + ['H1',0.0624015], + ['Fe54',7.1221325e-07], + ['Fe56',1.11802249e-05], + ['Fe57',2.5820015e-07], + ['Fe58',3.43617e-08], + ['Cr50',1.7025491450000002e-07], + ['Cr52',3.2831965549000006e-06], + ['Cr53',3.7228813410000004e-07], + ['Cr54',9.267039650000002e-08], + ['Ni58',1.89062485911e-06], + ['Ni60',7.2826531089e-07], + ['Ni61',3.1657188809999996e-08], + ['Ni62',1.0093697055000001e-07], + ['Ni64',2.5705670640000006e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=19.43, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-15.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-15.py new file mode 100644 index 0000000..d10f9fa --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-15.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (31.9 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.97235e-05], + ['Pu240',1.5133e-05], + ['Pu242',9.061670000000001e-07], + ['Am241',4.86126e-07], + ['N14',0.0015605227896200002], + ['N15',5.737210380000001e-06], + ['O16',0.035557218704699994], + ['O17',1.3481295299999999e-05], + ['H1',0.0629542], + ['Fe54',4.411952125e-07], + ['Fe56',6.925821305e-06], + ['Fe57',1.599474175e-07], + ['Fe58',2.1286065e-08], + ['Cr50',1.0546748850000001e-07], + ['Cr52',2.0338355337000003e-06], + ['Cr53',2.3062062330000003e-07], + ['Cr54',5.74063545e-08], + ['Ni58',1.17118137222e-06], + ['Ni60',4.5113696778e-07], + ['Ni61',1.9610611619999998e-08], + ['Ni62',6.252721110000001e-08], + ['Ni64',1.592383728e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=22.98, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-16.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-16.py new file mode 100644 index 0000000..4a71c3c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-16.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (26.9 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.03642e-05], + ['Pu240',1.27611e-05], + ['Pu242',7.641340000000001e-07], + ['Am241',4.09931e-07], + ['N14',0.0015229409579800002], + ['N15',5.5990420200000005e-06], + ['O16',0.0354792482667], + ['O17',1.34517333e-05], + ['H1',0.0630426], + ['Fe54',3.718641605e-07], + ['Fe56',5.8374720586e-06], + ['Fe57',1.348126871e-07], + ['Fe58',1.79410938e-08], + ['Cr50',8.889435500000002e-08], + ['Cr52',1.714239151e-06], + ['Cr53',1.9438095900000004e-07], + ['Cr54',4.838553500000001e-08], + ['Ni58',9.8714228076e-07], + ['Ni60',3.8024543923999996e-07], + ['Ni61',1.6529005959999998e-08], + ['Ni62',5.27017038e-08], + ['Ni64',1.3421570239999999e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=24.76, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-17.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-17.py new file mode 100644 index 0000000..3866f98 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-17.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (21.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',4.0627e-05], + ['Pu240',1.02943e-05], + ['Pu242',6.1642e-07], + ['Am241',3.30688e-07], + ['N14',0.00141229773413], + ['N15',5.19226587e-06], + ['O16',0.0354768491763], + ['O17',1.34508237e-05], + ['H1',0.06365], + ['Fe54',3.151396045e-07], + ['Fe56',4.9470178394000006e-06], + ['Fe57',1.1424821590000001e-07], + ['Fe58',1.52043402e-08], + ['Cr50',7.533404450000001e-08], + ['Cr52',1.4527420609e-06], + ['Cr53',1.647292881e-07], + ['Cr54',4.1004606500000004e-08], + ['Ni58',8.3656298565e-07], + ['Ni60',3.2224256435000004e-07], + ['Ni61',1.400766115e-08], + ['Ni62',4.466255325000001e-08], + ['Ni64',1.1374235600000002e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=28.8, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-18.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-18.py new file mode 100644 index 0000000..ee27ca0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-18.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (19.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.68825e-05], + ['Pu240',9.34548e-06], + ['Pu242',5.59608e-07], + ['Am241',3.0021e-07], + ['N14',0.00140826256928], + ['N15',5.17743072e-06], + ['O16',0.0353798859393], + ['O17',1.3414060700000003e-05], + ['H1',0.0634983], + ['Fe54',2.89928366e-07], + ['Fe56',4.5512553112e-06], + ['Fe57',1.0510833319999998e-07], + ['Fe58',1.39879896e-08], + ['Cr50',6.93075295e-08], + ['Cr52',1.3365267179000001e-06], + ['Cr53',1.515514011e-07], + ['Cr54',3.7724351500000005e-08], + ['Ni58',7.696365852600001e-07], + ['Ni60',2.9646263474000003e-07], + ['Ni61',1.288702546e-08], + ['Ni62',4.10894763e-08], + ['Ni64',1.046427824e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=31.52, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-19.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-19.py new file mode 100644 index 0000000..126c45d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-19.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (17.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.31381e-05], + ['Pu240',8.3967e-06], + ['Pu242',5.02795e-07], + ['Am241',2.69732e-07], + ['N14',0.0013797374409700001], + ['N15',5.07255903e-06], + ['O16',0.035362392571799996], + ['O17',1.34074282e-05], + ['H1',0.0636291], + ['Fe54',2.58414464e-07], + ['Fe56',4.0565544447999995e-06], + ['Fe57',9.368353279999999e-08], + ['Fe58',1.2467558399999998e-08], + ['Cr50',6.177373400000001e-08], + ['Cr52',1.1912449708e-06], + ['Cr53',1.350776172e-07], + ['Cr54',3.3623678e-08], + ['Ni58',6.8597688285e-07], + ['Ni60',2.6423706715e-07], + ['Ni61',1.148620235e-08], + ['Ni62',3.662303925e-08], + ['Ni64',9.3268084e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=35.53, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m5) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-2.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-2.py new file mode 100644 index 0000000..bdee779 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-2.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (17.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.31381e-05], + ['Pu240',8.3967e-06], + ['Pu242',5.02795e-07], + ['Am241',2.69732e-07], + ['N14',0.0013797374409700001], + ['N15',5.07255903e-06], + ['O16',0.035362392571799996], + ['O17',1.34074282e-05], + ['H1',0.0636291], + ['Fe54',2.58414464e-07], + ['Fe56',4.0565544447999995e-06], + ['Fe57',9.368353279999999e-08], + ['Fe58',1.2467558399999998e-08], + ['Cr50',6.177373400000001e-08], + ['Cr52',1.1912449708e-06], + ['Cr53',1.350776172e-07], + ['Cr54',3.3623678e-08], + ['Ni58',6.8597688285e-07], + ['Ni60',2.6423706715e-07], + ['Ni61',1.148620235e-08], + ['Ni62',3.662303925e-08], + ['Ni64',9.3268084e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=32.25, bc='interface') +s25 = mcdc.surface('plane-z', z=33.25, bc='interface') +s26 = mcdc.surface('plane-z', z=51.25, bc='interface') +s27 = mcdc.surface('plane-z', z=52.25, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s25 & -s26, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s25 & -s26, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s25 & -s26, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s25 & -s26, fill=m5) +c27 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s27, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s27, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s27, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s27, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s27 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s27 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s27 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-20.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-20.py new file mode 100644 index 0000000..461838d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-20.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (16.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.12659e-05], + ['Pu240',7.92231e-06], + ['Pu242',4.7438800000000005e-07], + ['Am241',2.54492e-07], + ['N14',0.00138024557284], + ['N15',5.07442716e-06], + ['O16',0.0353632922307], + ['O17',1.3407769299999999e-05], + ['H1',0.0636398], + ['Fe54',2.39505889e-07], + ['Fe56',3.7597302548e-06], + ['Fe57',8.682856780000001e-08], + ['Fe58',1.1555288400000001e-08], + ['Cr50',5.7254065e-08], + ['Cr52',1.104087653e-06], + ['Cr53',1.25194677e-07], + ['Cr54',3.1163605e-08], + ['Ni58',6.35785826787e-07], + ['Ni60',2.4490356221299997e-07], + ['Ni61',1.0645788276999998e-08], + ['Ni62',3.3943431435e-08], + ['Ni64',8.644391288e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=38.6, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m5) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-21.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-21.py new file mode 100644 index 0000000..a8bcd6b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-21.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (14.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',2.75215e-05], + ['Pu240',6.97353e-06], + ['Pu242',4.1757500000000003e-07], + ['Am241',2.24014e-07], + ['N14',0.00136515106729], + ['N15',5.01893271e-06], + ['O16',0.0353042146296], + ['O17',1.3385370399999998e-05], + ['H1',0.0636186], + ['Fe54',2.26900562e-07], + ['Fe56',3.5618535783999996e-06], + ['Fe57',8.22587324e-08], + ['Fe58',1.09471272e-08], + ['Cr50',5.4240373000000004e-08], + ['Cr52',1.0459716026e-06], + ['Cr53',1.1860478340000001e-07], + ['Cr54',2.9523241000000003e-08], + ['Ni58',6.023233073609999e-07], + ['Ni60',2.3201385963899998e-07], + ['Ni61',1.0085481830999998e-08], + ['Ni62',3.2156929305e-08], + ['Ni64',8.189421864e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=49.09, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m5) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-22.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-22.py new file mode 100644 index 0000000..a037d30 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-22.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (13.2 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',2.47132e-05], + ['Pu240',6.26195e-06], + ['Pu242',3.74965e-07], + ['Am241',2.01156e-07], + ['N14',0.0013666256460500002], + ['N15',5.024353950000001e-06], + ['O16',0.035287720883100004], + ['O17',1.3379116900000002e-05], + ['H1',0.0635948], + ['Fe54',2.07991987e-07], + ['Fe56',3.2650293884000003e-06], + ['Fe57',7.54037674e-08], + ['Fe58',1.0034857200000001e-08], + ['Cr50',4.972026950000001e-08], + ['Cr52',9.588059059e-07], + ['Cr53',1.087208931e-07], + ['Cr54',2.7062931500000002e-08], + ['Ni58',5.52129528222e-07], + ['Ni60',2.1267930577800002e-07], + ['Ni61',9.245022161999999e-09], + ['Ni62',2.9477176110000006e-08], + ['Ni64',7.506967728000001e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=69.57, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m5) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-23.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-23.py new file mode 100644 index 0000000..b9efffd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-23.py @@ -0,0 +1,196 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (13.2 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',2.47132e-05], + ['Pu240',6.26195e-06], + ['Pu242',3.74965e-07], + ['Am241',2.01156e-07], + ['N14',0.0013666256460500002], + ['N15',5.024353950000001e-06], + ['O16',0.035287720883100004], + ['O17',1.3379116900000002e-05], + ['H1',0.0635948], + ['Fe54',2.07991987e-07], + ['Fe56',3.2650293884000003e-06], + ['Fe57',7.54037674e-08], + ['Fe58',1.0034857200000001e-08], + ['Cr50',4.972026950000001e-08], + ['Cr52',9.588059059e-07], + ['Cr53',1.087208931e-07], + ['Cr54',2.7062931500000002e-08], + ['Ni58',5.52129528222e-07], + ['Ni60',2.1267930577800002e-07], + ['Ni61',9.245022161999999e-09], + ['Ni62',2.9477176110000006e-08], + ['Ni64',7.506967728000001e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +# Material Name: Steel (pool wall) +m6 = mcdc.material(nuclides=[ + ['Fe54',0.0049722246], + ['Fe56',0.07805329272], + ['Fe57',0.0018025909200000002], + ['Fe58',0.00023989176000000002], + ['C0',0.00055545]]) +# Material Name: Concrete +m7 = mcdc.material(nuclides=[ + ['H1',0.010349999999999998], + ['B10',1.6020000000000003e-06], + ['O16',0.04345352487], + ['O17',1.647513e-05], + ['Al27',0.001563], + ['Si28',0.013068945656000001], + ['Si29',0.0006636037720000001], + ['Si30',0.00043745057199999997], + ['Ca40',0.00622748984], + ['Ca42',4.156328000000001e-05], + ['Ca43',8.6724e-06], + ['Ca44',0.00013400464], + ['Ca46',2.5696000000000005e-07], + ['Ca48',1.201288e-05], + ['Fe54',4.4544745000000004e-05], + ['Fe56',0.0006992572339999999], + ['Fe57',1.6148899e-05], + ['Fe58',2.149122e-06]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-105.0, bc='interface') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=105.0, bc='interface') +s31 = mcdc.surface('plane-x', x=-655.0, bc='vacuum') +s32 = mcdc.surface('plane-x', x=-605.0, bc='interface') +s33 = mcdc.surface('plane-x', x=-105.8, bc='interface') +s34 = mcdc.surface('plane-x', x=105.8, bc='interface') +s35 = mcdc.surface('plane-x', x=605.0, bc='interface') +s36 = mcdc.surface('plane-x', x=655.0, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-160.0, bc='interface') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=160.0, bc='interface') +s41 = mcdc.surface('plane-y', y=-490.0, bc='vacuum') +s42 = mcdc.surface('plane-y', y=-440.0, bc='interface') +s43 = mcdc.surface('plane-y', y=-160.8, bc='interface') +s44 = mcdc.surface('plane-y', y=160.8, bc='interface') +s45 = mcdc.surface('plane-y', y=440.0, bc='interface') +s46 = mcdc.surface('plane-y', y=490.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-50.5, bc='interface') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=70.0, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='interface') +s51 = mcdc.surface('plane-z', z=-103.3, bc='vacuum') +s52 = mcdc.surface('plane-z', z=-63.3, bc='interface') +s53 = mcdc.surface('plane-z', z=-51.3, bc='interface') +s54 = mcdc.surface('plane-z', z=936.7, bc='interface') +s55 = mcdc.surface('plane-z', z=986.7, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m2) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s28, fill=m2) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s28, fill=m2) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s28, fill=m2) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s28, fill=m2) +c41 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s51 & -s52, fill=m7) +c42 = mcdc.cell(+s31 & -s32 & +s41 & -s46 & +s52 & -s54, fill=m7) +c43 = mcdc.cell(+s32 & -s35 & +s41 & -s42 & +s52 & -s54, fill=m7) +c44 = mcdc.cell(+s32 & -s35 & +s45 & -s46 & +s52 & -s54, fill=m7) +c45 = mcdc.cell(+s35 & -s36 & +s41 & -s46 & +s52 & -s54, fill=m7) +c46 = mcdc.cell(+s31 & -s36 & +s41 & -s46 & +s54 & -s55, fill=m7) +c51 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s52 & -s53, fill=m2) +c52 = mcdc.cell(+s32 & -s33 & +s42 & -s45 & +s53 & -s28, fill=m2) +c53 = mcdc.cell(+s33 & -s34 & +s42 & -s43 & +s53 & -s28, fill=m2) +c54 = mcdc.cell(+s33 & -s34 & +s44 & -s45 & +s53 & -s28, fill=m2) +c55 = mcdc.cell(+s34 & -s35 & +s42 & -s45 & +s53 & -s28, fill=m2) +c56 = mcdc.cell(+s32 & -s35 & +s42 & -s45 & +s28 & -s54, fill=m2) +c61 = mcdc.cell(+s33 & -s34 & +s43 & -s44 & +s53 & -s21, fill=m6) +c62 = mcdc.cell(+s33 & -s1 & +s43 & -s44 & +s21 & -s28, fill=m6) +c63 = mcdc.cell(+s1 & -s8 & +s43 & -s11 & +s21 & -s28, fill=m6) +c64 = mcdc.cell(+s1 & -s8 & +s18 & -s44 & +s21 & -s28, fill=m6) +c65 = mcdc.cell(+s8 & -s34 & +s43 & -s44 & +s21 & -s28, fill=m6) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-3.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-3.py new file mode 100644 index 0000000..23c80cc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-3.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (16.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',3.12659e-05], + ['Pu240',7.92231e-06], + ['Pu242',4.7438800000000005e-07], + ['Am241',2.54492e-07], + ['N14',0.00138024557284], + ['N15',5.07442716e-06], + ['O16',0.0353632922307], + ['O17',1.3407769299999999e-05], + ['H1',0.0636398], + ['Fe54',2.39505889e-07], + ['Fe56',3.7597302548e-06], + ['Fe57',8.682856780000001e-08], + ['Fe58',1.1555288400000001e-08], + ['Cr50',5.7254065e-08], + ['Cr52',1.104087653e-06], + ['Cr53',1.25194677e-07], + ['Cr54',3.1163605e-08], + ['Ni58',6.35785826787e-07], + ['Ni60',2.4490356221299997e-07], + ['Ni61',1.0645788276999998e-08], + ['Ni62',3.3943431435e-08], + ['Ni64',8.644391288e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=35.44, bc='interface') +s25 = mcdc.surface('plane-z', z=36.44, bc='interface') +s26 = mcdc.surface('plane-z', z=54.44, bc='interface') +s27 = mcdc.surface('plane-z', z=55.44, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s25 & -s26, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s25 & -s26, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s25 & -s26, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s25 & -s26, fill=m5) +c27 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s27, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s27, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s27, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s27, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s27 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s27 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s27 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-4.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-4.py new file mode 100644 index 0000000..7587def --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-4.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (14.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',2.75215e-05], + ['Pu240',6.97353e-06], + ['Pu242',4.1757500000000003e-07], + ['Am241',2.24014e-07], + ['N14',0.00136515106729], + ['N15',5.01893271e-06], + ['O16',0.0353042146296], + ['O17',1.3385370399999998e-05], + ['H1',0.0636186], + ['Fe54',2.26900562e-07], + ['Fe56',3.5618535783999996e-06], + ['Fe57',8.22587324e-08], + ['Fe58',1.09471272e-08], + ['Cr50',5.4240373000000004e-08], + ['Cr52',1.0459716026e-06], + ['Cr53',1.1860478340000001e-07], + ['Cr54',2.9523241000000003e-08], + ['Ni58',6.023233073609999e-07], + ['Ni60',2.3201385963899998e-07], + ['Ni61',1.0085481830999998e-08], + ['Ni62',3.2156929305e-08], + ['Ni64',8.189421864e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=45.68, bc='interface') +s25 = mcdc.surface('plane-z', z=46.68, bc='interface') +s26 = mcdc.surface('plane-z', z=64.68, bc='interface') +s27 = mcdc.surface('plane-z', z=65.68, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s25 & -s26, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s25 & -s26, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s25 & -s26, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s25 & -s26, fill=m5) +c27 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s27, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s27, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s27, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s27, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s27 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s27 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s27 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-5.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-5.py new file mode 100644 index 0000000..a1b3499 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-5.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (13.2 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',2.47132e-05], + ['Pu240',6.26195e-06], + ['Pu242',3.74965e-07], + ['Am241',2.01156e-07], + ['N14',0.0013666256460500002], + ['N15',5.024353950000001e-06], + ['O16',0.035287720883100004], + ['O17',1.3379116900000002e-05], + ['H1',0.0635948], + ['Fe54',2.07991987e-07], + ['Fe56',3.2650293884000003e-06], + ['Fe57',7.54037674e-08], + ['Fe58',1.0034857200000001e-08], + ['Cr50',4.972026950000001e-08], + ['Cr52',9.588059059e-07], + ['Cr53',1.087208931e-07], + ['Cr54',2.7062931500000002e-08], + ['Ni58',5.52129528222e-07], + ['Ni60',2.1267930577800002e-07], + ['Ni61',9.245022161999999e-09], + ['Ni62',2.9477176110000006e-08], + ['Ni64',7.506967728000001e-09]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=66.15, bc='interface') +s25 = mcdc.surface('plane-z', z=67.15, bc='interface') +s26 = mcdc.surface('plane-z', z=85.15, bc='interface') +s27 = mcdc.surface('plane-z', z=86.15, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s25 & -s26, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s25 & -s26, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s25 & -s26, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s25 & -s26, fill=m5) +c27 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s27, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s27, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s27, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s27, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s27 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s27 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s27 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s27 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-6.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-6.py new file mode 100644 index 0000000..1cda870 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-6.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (105.0 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.000196582], + ['Pu240',4.9810899999999994e-05], + ['Pu242',2.98268e-06], + ['Am241',1.6001e-06], + ['N14',0.00250472147441], + ['N15',9.20852559e-06], + ['O16',0.0372360821742], + ['O17',1.4117825799999997e-05], + ['H1',0.0607598], + ['Fe54',1.44964183e-06], + ['Fe56',2.2756276556e-05], + ['Fe57',5.25541666e-07], + ['Fe58',6.9939948e-08], + ['Cr50',3.4653677850000004e-07], + ['Cr52',6.6826168317000015e-06], + ['Cr53',7.577551053000001e-07], + ['Cr54',1.8862128450000003e-07], + ['Ni58',3.84817611861e-06], + ['Ni60',1.48231055139e-06], + ['Ni61',6.443501331e-08], + ['Ni62',2.0544701805000002e-07], + ['Ni64',5.232129864e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=16.32, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-7.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-7.py new file mode 100644 index 0000000..f7dd58b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-7.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (84.0 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',0.000157266], + ['Pu240',3.98488e-05], + ['Pu242',2.38614e-06], + ['Am241',1.28008e-06], + ['N14',0.00206327443982], + ['N15',7.585560180000001e-06], + ['O16',0.0366006231045], + ['O17',1.3876895500000002e-05], + ['H1',0.0619361], + ['Fe54',1.1849217799999999e-06], + ['Fe56',1.8600737896e-05], + ['Fe57',4.2957215600000004e-07], + ['Fe58',5.7168168000000007e-08], + ['Cr50',2.8325619850000004e-07], + ['Cr52',5.4623138357e-06], + ['Cr53',6.193825413e-07], + ['Cr54',1.5417742450000002e-07], + ['Ni58',3.1454659337399995e-06], + ['Ni60',1.21162784626e-06], + ['Ni61',5.266862354e-08], + ['Ni62',1.679306187e-07], + ['Ni64',4.276697776e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=16.32, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-8.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-8.py new file mode 100644 index 0000000..70346a2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-8.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (52.7 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',9.86655e-05], + ['Pu240',2.5000399999999995e-05], + ['Pu242',1.49702e-06], + ['Am241',8.03099e-07], + ['N14',0.0017784316548899999], + ['N15',6.538345109999999e-06], + ['O16',0.0359427725244], + ['O17',1.36274756e-05], + ['H1',0.0624015], + ['Fe54',7.1221325e-07], + ['Fe56',1.11802249e-05], + ['Fe57',2.5820015e-07], + ['Fe58',3.43617e-08], + ['Cr50',1.7025491450000002e-07], + ['Cr52',3.2831965549000006e-06], + ['Cr53',3.7228813410000004e-07], + ['Cr54',9.267039650000002e-08], + ['Ni58',1.89062485911e-06], + ['Ni60',7.2826531089e-07], + ['Ni61',3.1657188809999996e-08], + ['Ni62',1.0093697055000001e-07], + ['Ni64',2.5705670640000006e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=17.63, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-9.py b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-9.py new file mode 100644 index 0000000..84416df --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/mcdc/pu-sol-therm-012_case-9.py @@ -0,0 +1,139 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution (31.9 g/L) +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu239',5.97235e-05], + ['Pu240',1.5133e-05], + ['Pu242',9.061670000000001e-07], + ['Am241',4.86126e-07], + ['N14',0.0015605227896200002], + ['N15',5.737210380000001e-06], + ['O16',0.035557218704699994], + ['O17',1.3481295299999999e-05], + ['H1',0.0629542], + ['Fe54',4.411952125e-07], + ['Fe56',6.925821305e-06], + ['Fe57',1.599474175e-07], + ['Fe58',2.1286065e-08], + ['Cr50',1.0546748850000001e-07], + ['Cr52',2.0338355337000003e-06], + ['Cr53',2.3062062330000003e-07], + ['Cr54',5.74063545e-08], + ['Ni58',1.17118137222e-06], + ['Ni60',4.5113696778e-07], + ['Ni61',1.9610611619999998e-08], + ['Ni62',6.252721110000001e-08], + ['Ni64',1.592383728e-08]]) +# Material Name: Air +m2 = mcdc.material(nuclides=[ + ['O16',1.0784e-05], + ['N14',4.309e-05]]) +# Material Name: Stainless steel +m3 = mcdc.material(nuclides=[ + ['Fe54',0.003585556800000001], + ['Fe56',0.056285573760000006], + ['Fe57',0.0012998793600000002], + ['Fe58',0.00017299008000000001], + ['Cr50',0.0007157084], + ['Cr52',0.013801724080000001], + ['Cr53',0.00156500472], + ['Cr54',0.00038956280000000004], + ['Ni58',0.005517632744999999], + ['Ni60',0.0021253822549999997], + ['Ni61',9.2388895e-05], + ['Ni62',0.000294576225], + ['Ni64',7.501988e-05]]) +# Material Name: Lucoflex +m4 = mcdc.material(nuclides=[ + ['C0',0.027365], + ['H1',0.041047], + ['Cl35',0.010366126253999998], + ['Cl37',0.0033158737460000005]]) +# Material Name: Water +# S(a,b): c_H_in_H2O (Not Implemented) +m5 = mcdc.material(nuclides=[ + ['H1',0.066688], + ['O16',0.033331362624], + ['O17',1.2637376e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('plane-x', x=-90.5, bc='vacuum') +s2 = mcdc.surface('plane-x', x=-65.5, bc='interface') +s3 = mcdc.surface('plane-x', x=-65.0, bc='interface') +s4 = mcdc.surface('plane-x', x=-64.0, bc='interface') +s5 = mcdc.surface('plane-x', x=64.0, bc='interface') +s6 = mcdc.surface('plane-x', x=65.0, bc='interface') +s7 = mcdc.surface('plane-x', x=65.5, bc='interface') +s8 = mcdc.surface('plane-x', x=90.5, bc='vacuum') +s11 = mcdc.surface('plane-y', y=-90.5, bc='vacuum') +s12 = mcdc.surface('plane-y', y=-65.5, bc='interface') +s13 = mcdc.surface('plane-y', y=-65.0, bc='interface') +s14 = mcdc.surface('plane-y', y=-64.0, bc='interface') +s15 = mcdc.surface('plane-y', y=64.0, bc='interface') +s16 = mcdc.surface('plane-y', y=65.0, bc='interface') +s17 = mcdc.surface('plane-y', y=65.5, bc='interface') +s18 = mcdc.surface('plane-y', y=90.5, bc='vacuum') +s21 = mcdc.surface('plane-z', z=-25.5, bc='vacuum') +s22 = mcdc.surface('plane-z', z=-0.5, bc='interface') +s23 = mcdc.surface('plane-z', z=0.0, bc='interface') +s24 = mcdc.surface('plane-z', z=21.31, bc='interface') +s25 = mcdc.surface('plane-z', z=80.0, bc='interface') +s26 = mcdc.surface('plane-z', z=81.0, bc='interface') +s27 = mcdc.surface('plane-z', z=99.0, bc='interface') +s28 = mcdc.surface('plane-z', z=100.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s24 & -s25, fill=m2) +c10 = mcdc.cell(+s2 & -s7 & +s12 & -s17 & +s22 & -s23, fill=m3) +c11 = mcdc.cell(+s2 & -s3 & +s12 & -s17 & +s23 & -s28, fill=m3) +c12 = mcdc.cell(+s3 & -s6 & +s12 & -s13 & +s23 & -s28, fill=m3) +c13 = mcdc.cell(+s3 & -s6 & +s16 & -s17 & +s23 & -s28, fill=m3) +c14 = mcdc.cell(+s6 & -s7 & +s12 & -s17 & +s23 & -s28, fill=m3) +c20 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s25 & -s26, fill=m4) +c21 = mcdc.cell(+s3 & -s4 & +s13 & -s16 & +s26 & -s27, fill=m4) +c22 = mcdc.cell(+s4 & -s5 & +s13 & -s14 & +s26 & -s27, fill=m4) +c23 = mcdc.cell(+s4 & -s5 & +s15 & -s16 & +s26 & -s27, fill=m4) +c24 = mcdc.cell(+s5 & -s6 & +s13 & -s16 & +s26 & -s27, fill=m4) +c25 = mcdc.cell(+s3 & -s6 & +s13 & -s16 & +s27 & -s28, fill=m4) +c26 = mcdc.cell(+s4 & -s5 & +s14 & -s15 & +s26 & -s27, fill=m2) +c30 = mcdc.cell(+s1 & -s8 & +s11 & -s18 & +s21 & -s22, fill=m5) +c31 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s22 & -s24, fill=m5) +c32 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s22 & -s24, fill=m5) +c33 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s22 & -s24, fill=m5) +c34 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s22 & -s24, fill=m5) +c35 = mcdc.cell(+s1 & -s2 & +s11 & -s18 & +s24 & -s28, fill=m2) +c36 = mcdc.cell(+s2 & -s7 & +s11 & -s12 & +s24 & -s28, fill=m2) +c37 = mcdc.cell(+s2 & -s7 & +s17 & -s18 & +s24 & -s28, fill=m2) +c38 = mcdc.cell(+s7 & -s8 & +s11 & -s18 & +s24 & -s28, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-65.0,65.0], y=[-65.0,65.0], z=[0.0,23.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..d825e39 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (19.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.68825e-05) +mat.add_nuclide('Pu240', 9.34548e-06) +mat.add_nuclide('Pu241', 2.77030e-06) +mat.add_nuclide('Pu242', 5.59608e-07) +mat.add_nuclide('Am241', 3.00210e-07) +mat.add_element('N', 1.41344e-03) +mat.add_element('O', 3.53933e-02) +mat.add_nuclide('H1', 6.34983e-02) +mat.add_element('Fe', 4.96028e-06) +mat.add_element('Cr', 1.59511e-06) +mat.add_element('Ni', 1.13054e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/geometry.xml new file mode 100644 index 0000000..da41c08 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/geometry.xml @@ -0,0 +1,75 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/materials.xml new file mode 100644 index 0000000..53eb3be --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-1/plots.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/plots.xml new file mode 100644 index 0000000..b9ddb61 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/plots.xml @@ -0,0 +1,12 @@ + + + + + slice + xz + 0. 0. 40. + 181 150 + 500 500 + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-10/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..aa754cb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (26.9 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.03642e-05) +mat.add_nuclide('Pu240', 1.27611e-05) +mat.add_nuclide('Pu241', 3.78279e-06) +mat.add_nuclide('Pu242', 7.64134e-07) +mat.add_nuclide('Am241', 4.09931e-07) +mat.add_element('N', 1.52854e-03) +mat.add_element('O', 3.54927e-02) +mat.add_nuclide('H1', 6.30426e-02) +mat.add_element('Fe', 6.36209e-06) +mat.add_element('Cr', 2.04590e-06) +mat.add_element('Ni', 1.45004e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-10/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/geometry.xml new file mode 100644 index 0000000..c1793ab --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-10/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/materials.xml new file mode 100644 index 0000000..334ee89 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-10/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-10/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-11/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/generate_materials.py new file mode 100644 index 0000000..76fc447 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (21.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.06270e-05) +mat.add_nuclide('Pu240', 1.02943e-05) +mat.add_nuclide('Pu241', 3.05154e-06) +mat.add_nuclide('Pu242', 6.16420e-07) +mat.add_nuclide('Am241', 3.30688e-07) +mat.add_element('N', 1.41749e-03) +mat.add_element('O', 3.54903e-02) +mat.add_nuclide('H1', 6.36500e-02) +mat.add_element('Fe', 5.39161e-06) +mat.add_element('Cr', 1.73381e-06) +mat.add_element('Ni', 1.22885e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-11/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/geometry.xml new file mode 100644 index 0000000..50fb011 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-11/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/materials.xml new file mode 100644 index 0000000..a943939 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-11/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-11/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-12/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/generate_materials.py new file mode 100644 index 0000000..d825e39 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (19.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.68825e-05) +mat.add_nuclide('Pu240', 9.34548e-06) +mat.add_nuclide('Pu241', 2.77030e-06) +mat.add_nuclide('Pu242', 5.59608e-07) +mat.add_nuclide('Am241', 3.00210e-07) +mat.add_element('N', 1.41344e-03) +mat.add_element('O', 3.53933e-02) +mat.add_nuclide('H1', 6.34983e-02) +mat.add_element('Fe', 4.96028e-06) +mat.add_element('Cr', 1.59511e-06) +mat.add_element('Ni', 1.13054e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-12/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/geometry.xml new file mode 100644 index 0000000..86f9e9a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-12/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/materials.xml new file mode 100644 index 0000000..53eb3be --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-12/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-12/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-13/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/generate_materials.py new file mode 100644 index 0000000..7605776 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (13.2 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.47132e-05) +mat.add_nuclide('Pu240', 6.26195e-06) +mat.add_nuclide('Pu241', 1.85624e-06) +mat.add_nuclide('Pu242', 3.74965e-07) +mat.add_nuclide('Am241', 2.01156e-07) +mat.add_element('N', 1.37165e-03) +mat.add_element('O', 3.53011e-02) +mat.add_nuclide('H1', 6.35948e-02) +mat.add_element('Fe', 3.55846e-06) +mat.add_element('Cr', 1.14431e-06) +mat.add_element('Ni', 8.11038e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-13/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/geometry.xml new file mode 100644 index 0000000..2b8c7c6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-13/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/materials.xml new file mode 100644 index 0000000..118d38a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-13/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/settings.xml new file mode 100644 index 0000000..3c0b3a6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-13/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 67.46 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-14/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/generate_materials.py new file mode 100644 index 0000000..8eab1d8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (52.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.86655e-05) +mat.add_nuclide('Pu240', 2.50004e-05) +mat.add_nuclide('Pu241', 7.41089e-06) +mat.add_nuclide('Pu242', 1.49702e-06) +mat.add_nuclide('Am241', 8.03099e-07) +mat.add_element('N', 1.78497e-03) +mat.add_element('O', 3.59564e-02) +mat.add_nuclide('H1', 6.24015e-02) +mat.add_element('Fe', 1.21850e-05) +mat.add_element('Cr', 3.91841e-06) +mat.add_element('Ni', 2.77719e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-14/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/geometry.xml new file mode 100644 index 0000000..d2582f9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-14/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/materials.xml new file mode 100644 index 0000000..f5952e6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-14/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-14/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-15/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/generate_materials.py new file mode 100644 index 0000000..7695e4a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (31.9 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.97235e-05) +mat.add_nuclide('Pu240', 1.51330e-05) +mat.add_nuclide('Pu241', 4.48591e-06) +mat.add_nuclide('Pu242', 9.06167e-07) +mat.add_nuclide('Am241', 4.86126e-07) +mat.add_element('N', 1.56626e-03) +mat.add_element('O', 3.55707e-02) +mat.add_nuclide('H1', 6.29542e-02) +mat.add_element('Fe', 7.54825e-06) +mat.add_element('Cr', 2.42733e-06) +mat.add_element('Ni', 1.72038e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-15/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/geometry.xml new file mode 100644 index 0000000..f53c5f4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-15/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/materials.xml new file mode 100644 index 0000000..155197d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-15/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-15/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-16/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/generate_materials.py new file mode 100644 index 0000000..e86eb57 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (26.9 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.03642e-05) +mat.add_nuclide('Pu240', 1.27611e-05) +mat.add_nuclide('Pu241', 3.78279e-06) +mat.add_nuclide('Pu242', 7.64134e-07) +mat.add_nuclide('Am241', 4.09931e-07) +mat.add_element('N', 1.52854e-03) +mat.add_element('O', 3.54927e-02) +mat.add_nuclide('H1', 6.30426e-02) +mat.add_element('Fe', 6.36209e-06) +mat.add_element('Cr', 2.04590e-06) +mat.add_element('Ni', 1.45004e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-16/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/geometry.xml new file mode 100644 index 0000000..75f73ee --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-16/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/materials.xml new file mode 100644 index 0000000..4e72d2a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-16/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-16/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-17/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/generate_materials.py new file mode 100644 index 0000000..a57fe43 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (21.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 4.06270e-05) +mat.add_nuclide('Pu240', 1.02943e-05) +mat.add_nuclide('Pu241', 3.05154e-06) +mat.add_nuclide('Pu242', 6.16420e-07) +mat.add_nuclide('Am241', 3.30688e-07) +mat.add_element('N', 1.41749e-03) +mat.add_element('O', 3.54903e-02) +mat.add_nuclide('H1', 6.36500e-02) +mat.add_element('Fe', 5.39161e-06) +mat.add_element('Cr', 1.73381e-06) +mat.add_element('Ni', 1.22885e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-17/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/geometry.xml new file mode 100644 index 0000000..528f2c0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-17/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/materials.xml new file mode 100644 index 0000000..bf68f39 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-17/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-17/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-18/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/generate_materials.py new file mode 100644 index 0000000..bbb88ef --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (19.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.68825e-05) +mat.add_nuclide('Pu240', 9.34548e-06) +mat.add_nuclide('Pu241', 2.77030e-06) +mat.add_nuclide('Pu242', 5.59608e-07) +mat.add_nuclide('Am241', 3.00210e-07) +mat.add_element('N', 1.41344e-03) +mat.add_element('O', 3.53933e-02) +mat.add_nuclide('H1', 6.34983e-02) +mat.add_element('Fe', 4.96028e-06) +mat.add_element('Cr', 1.59511e-06) +mat.add_element('Ni', 1.13054e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-18/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/geometry.xml new file mode 100644 index 0000000..97cf36f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-18/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/materials.xml new file mode 100644 index 0000000..3232370 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-18/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-18/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-19/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/generate_materials.py new file mode 100644 index 0000000..906c7d5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (17.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.31381e-05) +mat.add_nuclide('Pu240', 8.39670e-06) +mat.add_nuclide('Pu241', 2.48905e-06) +mat.add_nuclide('Pu242', 5.02795e-07) +mat.add_nuclide('Am241', 2.69732e-07) +mat.add_element('N', 1.38481e-03) +mat.add_element('O', 3.53758e-02) +mat.add_nuclide('H1', 6.36291e-02) +mat.add_element('Fe', 4.42112e-06) +mat.add_element('Cr', 1.42172e-06) +mat.add_element('Ni', 1.00765e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-19/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/geometry.xml new file mode 100644 index 0000000..0007863 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-19/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/materials.xml new file mode 100644 index 0000000..7f91eb8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-19/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-19/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..6580704 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (17.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.31381e-05) +mat.add_nuclide('Pu240', 8.39670e-06) +mat.add_nuclide('Pu241', 2.48905e-06) +mat.add_nuclide('Pu242', 5.02795e-07) +mat.add_nuclide('Am241', 2.69732e-07) +mat.add_element('N', 1.38481e-03) +mat.add_element('O', 3.53758e-02) +mat.add_nuclide('H1', 6.36291e-02) +mat.add_element('Fe', 4.42112e-06) +mat.add_element('Cr', 1.42172e-06) +mat.add_element('Ni', 1.00765e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/geometry.xml new file mode 100644 index 0000000..45f309b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/geometry.xml @@ -0,0 +1,75 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/materials.xml new file mode 100644 index 0000000..c600f3d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-20/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/generate_materials.py new file mode 100644 index 0000000..66253bd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (16.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.12659e-05) +mat.add_nuclide('Pu240', 7.92231e-06) +mat.add_nuclide('Pu241', 2.34842e-06) +mat.add_nuclide('Pu242', 4.74388e-07) +mat.add_nuclide('Am241', 2.54492e-07) +mat.add_element('N', 1.38532e-03) +mat.add_element('O', 3.53767e-02) +mat.add_nuclide('H1', 6.36398e-02) +mat.add_element('Fe', 4.09762e-06) +mat.add_element('Cr', 1.31770e-06) +mat.add_element('Ni', 9.33923e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-20/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/geometry.xml new file mode 100644 index 0000000..dccf0b0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-20/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/materials.xml new file mode 100644 index 0000000..f3b5535 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-20/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-20/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-21/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/generate_materials.py new file mode 100644 index 0000000..18fedc6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (14.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.75215e-05) +mat.add_nuclide('Pu240', 6.97353e-06) +mat.add_nuclide('Pu241', 2.06717e-06) +mat.add_nuclide('Pu242', 4.17575e-07) +mat.add_nuclide('Am241', 2.24014e-07) +mat.add_element('N', 1.37017e-03) +mat.add_element('O', 3.53176e-02) +mat.add_nuclide('H1', 6.36186e-02) +mat.add_element('Fe', 3.88196e-06) +mat.add_element('Cr', 1.24834e-06) +mat.add_element('Ni', 8.84769e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-21/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/geometry.xml new file mode 100644 index 0000000..9ea66c8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-21/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/materials.xml new file mode 100644 index 0000000..fdd0b55 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-21/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-21/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-22/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/generate_materials.py new file mode 100644 index 0000000..228151f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (13.2 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.47132e-05) +mat.add_nuclide('Pu240', 6.26195e-06) +mat.add_nuclide('Pu241', 1.85624e-06) +mat.add_nuclide('Pu242', 3.74965e-07) +mat.add_nuclide('Am241', 2.01156e-07) +mat.add_element('N', 1.37165e-03) +mat.add_element('O', 3.53011e-02) +mat.add_nuclide('H1', 6.35948e-02) +mat.add_element('Fe', 3.55846e-06) +mat.add_element('Cr', 1.14431e-06) +mat.add_element('Ni', 8.11038e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-22/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/geometry.xml new file mode 100644 index 0000000..8cd9a1b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-22/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/materials.xml new file mode 100644 index 0000000..751c2b6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-22/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-22/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-23/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/generate_materials.py new file mode 100644 index 0000000..228151f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/generate_materials.py @@ -0,0 +1,72 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (13.2 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.47132e-05) +mat.add_nuclide('Pu240', 6.26195e-06) +mat.add_nuclide('Pu241', 1.85624e-06) +mat.add_nuclide('Pu242', 3.74965e-07) +mat.add_nuclide('Am241', 2.01156e-07) +mat.add_element('N', 1.37165e-03) +mat.add_element('O', 3.53011e-02) +mat.add_nuclide('H1', 6.35948e-02) +mat.add_element('Fe', 3.55846e-06) +mat.add_element('Cr', 1.14431e-06) +mat.add_element('Ni', 8.11038e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(6) +mat.name = "Steel (pool wall)" +mat.set_density('sum') +mat.add_element('Fe', 8.5068e-02) +mat.add_element('C', 5.5545e-04) +mats.append(mat) + +mat = openmc.Material(7) +mat.name = "Concrete" +mat.set_density('sum') +mat.add_nuclide('H1', 1.035e-02) +mat.add_nuclide('B10', 1.602e-06) +mat.add_element('O', 4.347e-02) +mat.add_element('Al', 1.563e-03) +mat.add_element('Si', 1.417e-02) +mat.add_element('Ca', 6.424e-03) +mat.add_element('Fe', 7.621e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-23/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/geometry.xml new file mode 100644 index 0000000..de1cdb9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/geometry.xml @@ -0,0 +1,107 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-23/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/materials.xml new file mode 100644 index 0000000..751c2b6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/materials.xml @@ -0,0 +1,94 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-23/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-23/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..3795543 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (16.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 3.12659e-05) +mat.add_nuclide('Pu240', 7.92231e-06) +mat.add_nuclide('Pu241', 2.34842e-06) +mat.add_nuclide('Pu242', 4.74388e-07) +mat.add_nuclide('Am241', 2.54492e-07) +mat.add_element('N', 1.38532e-03) +mat.add_element('O', 3.53767e-02) +mat.add_nuclide('H1', 6.36398e-02) +mat.add_element('Fe', 4.09762e-06) +mat.add_element('Cr', 1.31770e-06) +mat.add_element('Ni', 9.33923e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/geometry.xml new file mode 100644 index 0000000..973e387 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/geometry.xml @@ -0,0 +1,75 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/materials.xml new file mode 100644 index 0000000..f6b26e2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..d4f0f70 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (14.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.75215e-05) +mat.add_nuclide('Pu240', 6.97353e-06) +mat.add_nuclide('Pu241', 2.06717e-06) +mat.add_nuclide('Pu242', 4.17575e-07) +mat.add_nuclide('Am241', 2.24014e-07) +mat.add_element('N', 1.37017e-03) +mat.add_element('O', 3.53176e-02) +mat.add_nuclide('H1', 6.36186e-02) +mat.add_element('Fe', 3.88196e-06) +mat.add_element('Cr', 1.24834e-06) +mat.add_element('Ni', 8.84769e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/geometry.xml new file mode 100644 index 0000000..b267841 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/geometry.xml @@ -0,0 +1,75 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/materials.xml new file mode 100644 index 0000000..a77b0fa --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..7605776 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (13.2 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 2.47132e-05) +mat.add_nuclide('Pu240', 6.26195e-06) +mat.add_nuclide('Pu241', 1.85624e-06) +mat.add_nuclide('Pu242', 3.74965e-07) +mat.add_nuclide('Am241', 2.01156e-07) +mat.add_element('N', 1.37165e-03) +mat.add_element('O', 3.53011e-02) +mat.add_nuclide('H1', 6.35948e-02) +mat.add_element('Fe', 3.55846e-06) +mat.add_element('Cr', 1.14431e-06) +mat.add_element('Ni', 8.11038e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/geometry.xml new file mode 100644 index 0000000..26a389e --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/geometry.xml @@ -0,0 +1,75 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/materials.xml new file mode 100644 index 0000000..118d38a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..d11daf9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (105.0 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.96582e-04) +mat.add_nuclide('Pu240', 4.98109e-05) +mat.add_nuclide('Pu241', 1.47655e-05) +mat.add_nuclide('Pu242', 2.98268e-06) +mat.add_nuclide('Am241', 1.60010e-06) +mat.add_element('N', 2.51393e-03) +mat.add_element('O', 3.72502e-02) +mat.add_nuclide('H1', 6.07598e-02) +mat.add_element('Fe', 2.48014e-05) +mat.add_element('Cr', 7.97553e-06) +mat.add_element('Ni', 5.65269e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/geometry.xml new file mode 100644 index 0000000..412ec0d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/materials.xml new file mode 100644 index 0000000..e88c648 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-6/plots.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/plots.xml new file mode 100644 index 0000000..b9ddb61 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/plots.xml @@ -0,0 +1,12 @@ + + + + + slice + xz + 0. 0. 40. + 181 150 + 500 500 + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-6/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..f3dabe4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (84.0 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 1.57266e-04) +mat.add_nuclide('Pu240', 3.98488e-05) +mat.add_nuclide('Pu241', 1.18124e-05) +mat.add_nuclide('Pu242', 2.38614e-06) +mat.add_nuclide('Am241', 1.28008e-06) +mat.add_element('N', 2.07086e-03) +mat.add_element('O', 3.66145e-02) +mat.add_nuclide('H1', 6.19361e-02) +mat.add_element('Fe', 2.02724e-05) +mat.add_element('Cr', 6.51913e-06) +mat.add_element('Ni', 4.62046e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/geometry.xml new file mode 100644 index 0000000..5bb623d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/materials.xml new file mode 100644 index 0000000..b44cbc3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-7/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..becc49a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (52.7 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 9.86655e-05) +mat.add_nuclide('Pu240', 2.50004e-05) +mat.add_nuclide('Pu241', 7.41089e-06) +mat.add_nuclide('Pu242', 1.49702e-06) +mat.add_nuclide('Am241', 8.03099e-07) +mat.add_element('N', 1.78497e-03) +mat.add_element('O', 3.59564e-02) +mat.add_nuclide('H1', 6.24015e-02) +mat.add_element('Fe', 1.21850e-05) +mat.add_element('Cr', 3.91841e-06) +mat.add_element('Ni', 2.77719e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/geometry.xml new file mode 100644 index 0000000..0cc3192 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/materials.xml new file mode 100644 index 0000000..d60cff8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-8/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-9/generate_materials.py b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..490cc5b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/generate_materials.py @@ -0,0 +1,53 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution (31.9 g/L)" +mat.set_density('sum') +mat.add_nuclide('Pu239', 5.97235e-05) +mat.add_nuclide('Pu240', 1.51330e-05) +mat.add_nuclide('Pu241', 4.48591e-06) +mat.add_nuclide('Pu242', 9.06167e-07) +mat.add_nuclide('Am241', 4.86126e-07) +mat.add_element('N', 1.56626e-03) +mat.add_element('O', 3.55707e-02) +mat.add_nuclide('H1', 6.29542e-02) +mat.add_element('Fe', 7.54825e-06) +mat.add_element('Cr', 2.42733e-06) +mat.add_element('Ni', 1.72038e-06) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Air" +mat.set_density('sum') +mat.add_nuclide('O16', 1.0784e-05) +mat.add_nuclide('N14', 4.3090e-05) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.1344e-02) +mat.add_element('Cr', 1.6472e-02) +mat.add_element('Ni', 8.1050e-03) +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Lucoflex" +mat.set_density('sum') +mat.add_element('C', 2.7365e-02) +mat.add_nuclide('H1', 4.1047e-02) +mat.add_element('Cl', 1.3682e-02) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "Water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6688e-02) +mat.add_element('O', 3.3344e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-9/geometry.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/geometry.xml new file mode 100644 index 0000000..a2da9a6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/geometry.xml @@ -0,0 +1,72 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-9/materials.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/materials.xml new file mode 100644 index 0000000..41dd3c7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-012/openmc/case-9/settings.xml b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/settings.xml new file mode 100644 index 0000000..3708614 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-012/openmc/case-9/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -65 -65 0 65 65 23 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-1.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-1.py new file mode 100644 index 0000000..d08bd7b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-1.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',7.1867e-07], + ['Pu239',0.00014582], + ['Pu240',0.00015056], + ['Pu242',1.6381e-05], + ['Am241',3.7773000000000002e-06], + ['Gd152',9.543400000000002e-11], + ['Gd154',1.0402306e-09], + ['Gd155',7.062116e-09], + ['Gd156',9.767669900000001e-09], + ['Gd157',7.4677105e-09], + ['Gd158',1.18529028e-08], + ['Gd160',1.04309362e-08], + ['H1',0.055235], + ['N14',0.0044245333496000004], + ['N15',1.62666504e-05], + ['O16',0.039413056788], + ['O17',1.4943211999999999e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=76.277, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-2.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-2.py new file mode 100644 index 0000000..e328716 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-2.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',5.9547e-07], + ['Pu239',0.00012082000000000001], + ['Pu240',0.00012475], + ['Pu242',1.3573e-05], + ['Am241',3.1297999999999997e-06], + ['Gd152',7.9074e-11], + ['Gd154',8.619065999999999e-10], + ['Gd155',5.851475999999999e-09], + ['Gd156',8.093223899999999e-09], + ['Gd157',6.187540499999999e-09], + ['Gd158',9.8209908e-09], + ['Gd160',8.642788199999999e-09], + ['H1',0.05723], + ['N14',0.0036543648486000004], + ['N15',1.3435151400000002e-05], + ['O16',0.038357457012], + ['O17',1.4542988000000002e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=72.727, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-3.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-3.py new file mode 100644 index 0000000..4019d45 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-3.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',5.0954e-07], + ['Pu239',0.00010338], + ['Pu240',0.00010675], + ['Pu242',1.1614e-05], + ['Am241',2.6781e-06], + ['Gd152',6.766400000000001e-11], + ['Gd154',7.375376e-10], + ['Gd155',5.007136e-09], + ['Gd156',6.925410400000001e-09], + ['Gd157',5.294708e-09], + ['Gd158',8.4038688e-09], + ['Gd160',7.3956751999999995e-09], + ['H1',0.05839099999999999], + ['N14',0.0032034227224], + ['N15',1.17772776e-05], + ['O16',0.037721698056], + ['O17',1.4301944e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=70.437, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-4.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-4.py new file mode 100644 index 0000000..76d7ad7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-4.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.3906e-07], + ['Pu239',8.9084e-05], + ['Pu240',9.1981e-05], + ['Pu242',1.0008e-05], + ['Am241',2.3077e-06], + ['Gd152',5.8304e-11], + ['Gd154',6.355135999999999e-10], + ['Gd155',4.314496e-09], + ['Gd156',5.9674144e-09], + ['Gd157',4.562288e-09], + ['Gd158',7.2413568e-09], + ['Gd160',6.3726272000000005e-09], + ['H1',0.05960699999999999], + ['N14',0.002734945065], + ['N15',1.0054935e-05], + ['O16',0.037084939479], + ['O17',1.4060521e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=69.177, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-5.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-5.py new file mode 100644 index 0000000..42a6177 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-5.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.8829e-07], + ['Pu239',7.8783e-05], + ['Pu240',8.1345e-05], + ['Pu242',8.8504e-06], + ['Am241',2.0408e-06], + ['Gd152',5.1562000000000005e-11], + ['Gd154',5.620258e-10], + ['Gd155',3.815588e-09], + ['Gd156',5.2773707e-09], + ['Gd157',4.0347265e-09], + ['Gd158',6.404000400000001e-09], + ['Gd160',5.6357266e-09], + ['H1',0.060457], + ['N14',0.0024071501920000004], + ['N15',8.849808000000001e-06], + ['O16',0.036637109271], + ['O17',1.3890729000000002e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=69.467, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-6.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-6.py new file mode 100644 index 0000000..4cd7382 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-6.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',3.3429e-07], + ['Pu239',6.7826e-05], + ['Pu240',7.0032e-05], + ['Pu242',7.6195e-06], + ['Am241',1.757e-06], + ['Gd152',4.439e-11], + ['Gd154',4.83851e-10], + ['Gd155',3.28486e-09], + ['Gd156',4.5433165e-09], + ['Gd157',3.4735175000000003e-09], + ['Gd158',5.513238000000001e-09], + ['Gd160',4.851827e-09], + ['H1',0.061242], + ['N14',0.0021030681396], + ['N15',7.7318604e-06], + ['O16',0.036213269967], + ['O17',1.3730033000000001e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=71.297, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-7.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-7.py new file mode 100644 index 0000000..3aac58a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-7.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',2.8921e-07], + ['Pu239',5.868100000000001e-05], + ['Pu240',6.0589999999999994e-05], + ['Pu242',6.5922e-06], + ['Am241',1.5201e-06], + ['Gd152',3.8406e-11], + ['Gd154',4.1862539999999996e-10], + ['Gd155',2.842044e-09], + ['Gd156',3.9308540999999996e-09], + ['Gd157',3.0052695e-09], + ['Gd158',4.7700252000000005e-09], + ['Gd160',4.1977757999999994e-09], + ['H1',0.06203299999999999], + ['N14',0.001798388285], + ['N15',6.611714999999999e-06], + ['O16',0.035800426494], + ['O17',1.3573506e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=75.007, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-8.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-8.py new file mode 100644 index 0000000..c548e16 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-8.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',2.404e-07], + ['Pu239',4.8776e-05], + ['Pu240',5.0362e-05], + ['Pu242',5.4795e-06], + ['Am241',1.2635e-06], + ['Gd152',3.1922e-11], + ['Gd154',3.479498e-10], + ['Gd155',2.362228e-09], + ['Gd156',3.2672167e-09], + ['Gd157',2.4978965e-09], + ['Gd158',3.9647124e-09], + ['Gd160',3.4890745999999996e-09], + ['H1',0.062825], + ['N14',0.001492512826], + ['N15',5.487174e-06], + ['O16',0.035381585295000004], + ['O17',1.3414705000000001e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=85.647, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-9.py b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-9.py new file mode 100644 index 0000000..884bfc2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/mcdc/pu-sol-therm-018_case-9.py @@ -0,0 +1,103 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',2.0831e-07], + ['Pu239',4.2266e-05], + ['Pu240',4.3641e-05], + ['Pu242',4.7482e-06], + ['Am241',1.0949e-06], + ['Gd152',2.7662000000000002e-11], + ['Gd154',3.015158e-10], + ['Gd155',2.046988e-09], + ['Gd156',2.8312057e-09], + ['Gd157',2.1645515e-09], + ['Gd158',3.4356204e-09], + ['Gd160',3.0234565999999996e-09], + ['H1',0.063362], + ['N14',0.0012854739974000001], + ['N15',4.7260026e-06], + ['O16',0.035098692551999995], + ['O17',1.3307447999999999e-05]]) +# Material Name: steel clad +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: water +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=103.097, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-20.0,20.0], y=[-20.0,20.0], z=[0.0,143.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..65994e2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 7.1867e-07) +mat.add_nuclide('Pu239', 1.4582e-04) +mat.add_nuclide('Pu240', 1.5056e-04) +mat.add_nuclide('Pu241', 3.8051e-05) +mat.add_nuclide('Pu242', 1.6381e-05) +mat.add_nuclide('Am241', 3.7773e-06) +mat.add_element('Gd', 4.7717e-08) +mat.add_nuclide('H1', 5.5235e-02) +mat.add_element('N', 4.4408e-03) +mat.add_element('O', 3.9428e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/geometry.xml new file mode 100644 index 0000000..ad0d569 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/materials.xml new file mode 100644 index 0000000..381c5e6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-1/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..ecf633f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 5.9547e-07) +mat.add_nuclide('Pu239', 1.2082e-04) +mat.add_nuclide('Pu240', 1.2475e-04) +mat.add_nuclide('Pu241', 3.1528e-05) +mat.add_nuclide('Pu242', 1.3573e-05) +mat.add_nuclide('Am241', 3.1298e-06) +mat.add_element('Gd', 3.9537e-08) +mat.add_nuclide('H1', 5.7230e-02) +mat.add_element('N', 3.6678e-03) +mat.add_element('O', 3.8372e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/geometry.xml new file mode 100644 index 0000000..5383e8f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/materials.xml new file mode 100644 index 0000000..276fbf1 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-2/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..2ad3f83 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 5.0954e-07) +mat.add_nuclide('Pu239', 1.0338e-04) +mat.add_nuclide('Pu240', 1.0675e-04) +mat.add_nuclide('Pu241', 2.6978e-05) +mat.add_nuclide('Pu242', 1.1614e-05) +mat.add_nuclide('Am241', 2.6781e-06) +mat.add_element('Gd', 3.3832e-08) +mat.add_nuclide('H1', 5.8391e-02) +mat.add_element('N', 3.2152e-03) +mat.add_element('O', 3.7736e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/geometry.xml new file mode 100644 index 0000000..154f261 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/materials.xml new file mode 100644 index 0000000..15f7d02 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-3/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..015f494 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.3906e-07) +mat.add_nuclide('Pu239', 8.9084e-05) +mat.add_nuclide('Pu240', 9.1981e-05) +mat.add_nuclide('Pu241', 2.3247e-05) +mat.add_nuclide('Pu242', 1.0008e-05) +mat.add_nuclide('Am241', 2.3077e-06) +mat.add_element('Gd', 2.9152e-08) +mat.add_nuclide('H1', 5.9607e-02) +mat.add_element('N', 2.7450e-03) +mat.add_element('O', 3.7099e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/geometry.xml new file mode 100644 index 0000000..694afff --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/materials.xml new file mode 100644 index 0000000..45c3a0d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-4/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..a3f10aa --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.8829e-07) +mat.add_nuclide('Pu239', 7.8783e-05) +mat.add_nuclide('Pu240', 8.1345e-05) +mat.add_nuclide('Pu241', 2.0559e-05) +mat.add_nuclide('Pu242', 8.8504e-06) +mat.add_nuclide('Am241', 2.0408e-06) +mat.add_element('Gd', 2.5781e-08) +mat.add_nuclide('H1', 6.0457e-02) +mat.add_element('N', 2.4160e-03) +mat.add_element('O', 3.6651e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/geometry.xml new file mode 100644 index 0000000..e6d243a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/materials.xml new file mode 100644 index 0000000..8c8c02a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-5/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..3026fc6 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 3.3429e-07) +mat.add_nuclide('Pu239', 6.7826e-05) +mat.add_nuclide('Pu240', 7.0032e-05) +mat.add_nuclide('Pu241', 1.7699e-05) +mat.add_nuclide('Pu242', 7.6195e-06) +mat.add_nuclide('Am241', 1.7570e-06) +mat.add_element('Gd', 2.2195e-08) +mat.add_nuclide('H1', 6.1242e-02) +mat.add_element('N', 2.1108e-03) +mat.add_element('O', 3.6227e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/geometry.xml new file mode 100644 index 0000000..f927424 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/materials.xml new file mode 100644 index 0000000..6157beb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-6/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..5cf60d9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 2.8921e-07) +mat.add_nuclide('Pu239', 5.8681e-05) +mat.add_nuclide('Pu240', 6.0590e-05) +mat.add_nuclide('Pu241', 1.5313e-05) +mat.add_nuclide('Pu242', 6.5922e-06) +mat.add_nuclide('Am241', 1.5201e-06) +mat.add_element('Gd', 1.9203e-08) +mat.add_nuclide('H1', 6.2033e-02) +mat.add_element('N', 1.8050e-03) +mat.add_element('O', 3.5814e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/geometry.xml new file mode 100644 index 0000000..bb99854 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/materials.xml new file mode 100644 index 0000000..8ab1c5b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-7/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..2ff8747 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 2.4040e-07) +mat.add_nuclide('Pu239', 4.8776e-05) +mat.add_nuclide('Pu240', 5.0362e-05) +mat.add_nuclide('Pu241', 1.2728e-05) +mat.add_nuclide('Pu242', 5.4795e-06) +mat.add_nuclide('Am241', 1.2635e-06) +mat.add_element('Gd', 1.5961e-08) +mat.add_nuclide('H1', 6.2825e-02) +mat.add_element('N', 1.4980e-03) +mat.add_element('O', 3.5395e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/geometry.xml new file mode 100644 index 0000000..9858d2d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/materials.xml new file mode 100644 index 0000000..a1c9f34 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-8/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-9/generate_materials.py b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..02d38c8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/generate_materials.py @@ -0,0 +1,37 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 2.0831e-07) +mat.add_nuclide('Pu239', 4.2266e-05) +mat.add_nuclide('Pu240', 4.3641e-05) +mat.add_nuclide('Pu241', 1.1029e-05) +mat.add_nuclide('Pu242', 4.7482e-06) +mat.add_nuclide('Am241', 1.0949e-06) +mat.add_element('Gd', 1.3831e-08) +mat.add_nuclide('H1', 6.3362e-02) +mat.add_element('N', 1.2902e-03) +mat.add_element('O', 3.5112e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "steel clad" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "water" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-9/geometry.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/geometry.xml new file mode 100644 index 0000000..83d9e31 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-9/materials.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/materials.xml new file mode 100644 index 0000000..cef8c0f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/materials.xml @@ -0,0 +1,48 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-018/openmc/case-9/settings.xml b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/settings.xml new file mode 100644 index 0000000..4c89e87 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-018/openmc/case-9/settings.xml @@ -0,0 +1,21 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + + -20. -20. 0. + 20. 20. 143. + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-021/mcdc/pu-sol-therm-021_case-1.py b/icsbep/openmc/pu-sol-therm-021/mcdc/pu-sol-therm-021_case-1.py new file mode 100644 index 0000000..0c2b367 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/mcdc/pu-sol-therm-021_case-1.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',5.9197e-09], + ['Pu239',9.3366e-05], + ['Pu240',4.568e-06], + ['Pu242',8.7324e-09], + ['N14',0.00063382], + ['H1',0.065515], + ['O16',0.034538]]) +# Material Name: 304L Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.3304, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.4523, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-021/mcdc/pu-sol-therm-021_case-3.py b/icsbep/openmc/pu-sol-therm-021/mcdc/pu-sol-therm-021_case-3.py new file mode 100644 index 0000000..d4b36fd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/mcdc/pu-sol-therm-021_case-3.py @@ -0,0 +1,66 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Plutonium nitrate solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',2.6153e-08], + ['Pu239',0.00041249], + ['Pu240',2.0181e-05], + ['Pu242',3.8579e-08], + ['N14',0.0046867], + ['H1',0.054376999999999995], + ['O16',0.039773]]) +# Material Name: 304L Stainless Steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.00346929975], + ['Fe56',0.0544605867], + ['Fe57',0.00125773245], + ['Fe58',0.0001673811], + ['Cr50',0.0007572465999999999], + ['Cr52',0.014602746920000001], + ['Cr53',0.0016558342799999999], + ['Cr54',0.0004121722], + ['Ni58',0.0052557409107], + ['Ni60',0.0020245019893], + ['Ni61',8.800369969999998e-05], + ['Ni62',0.00028059430350000004], + ['Ni64',7.14590968e-05], + ['Mn55',0.0017363]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.3163, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=19.4382, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..de6a27d --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 5.9197e-09) +mat.add_nuclide('Pu239', 9.3366e-05) +mat.add_nuclide('Pu240', 4.5680e-06) +mat.add_nuclide('Pu241', 2.7573e-07) +mat.add_nuclide('Pu242', 8.7324e-09) +mat.add_nuclide('N14', 6.3382e-04) +mat.add_nuclide('H1', 6.5515e-02) +mat.add_nuclide('O16', 3.4538e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/geometry.xml new file mode 100644 index 0000000..1953d22 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/materials.xml new file mode 100644 index 0000000..0c306a9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..b2728ae --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Plutonium nitrate solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 2.6153e-08) +mat.add_nuclide('Pu239', 4.1249e-04) +mat.add_nuclide('Pu240', 2.0181e-05) +mat.add_nuclide('Pu241', 1.2181e-06) +mat.add_nuclide('Pu242', 3.8579e-08) +mat.add_nuclide('N14', 4.6867e-03) +mat.add_nuclide('H1', 5.4377e-02) +mat.add_nuclide('O16', 3.9773e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L Stainless Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9355e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Ni', 7.7203e-03) +mat.add_element('Mn', 1.7363e-03) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/geometry.xml new file mode 100644 index 0000000..6c844fb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/materials.xml new file mode 100644 index 0000000..b8bae65 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-021/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-021/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-1.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-1.py new file mode 100644 index 0000000..05a053f --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-1.py @@ -0,0 +1,95 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.2912e-07], + ['Pu239',0.00026498], + ['Pu240',2.4383e-05], + ['Pu242',1.4141e-07], + ['H1',0.060973], + ['N14',0.0023118007411], + ['N15',8.4992589e-06], + ['O16',0.03687601869], + ['O17',1.398131e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=37.617, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-10.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-10.py new file mode 100644 index 0000000..91f6935 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-10.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4251999999999997e-07], + ['Gd152',6.2882e-08], + ['Gd154',6.854138e-07], + ['Gd155',4.653268e-06], + ['Gd156',6.4359726999999995e-06], + ['Gd157',4.9205165e-06], + ['Gd158',7.8099444e-06], + ['Gd160',6.873002599999999e-06], + ['H1',0.048972999999999996], + ['N14',0.0061360410482], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=55.017, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-11.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-11.py new file mode 100644 index 0000000..2a8a13a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-11.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4252e-07], + ['Gd152',7.5672e-08], + ['Gd154',8.248248e-07], + ['Gd155',5.599728e-06], + ['Gd156',7.7450292e-06], + ['Gd157',5.921334e-06], + ['Gd158',9.3984624e-06], + ['Gd160',8.2709496e-06], + ['H1',0.048973], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=58.217, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-12.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-12.py new file mode 100644 index 0000000..c3e7b6b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-12.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4251999999999997e-07], + ['Gd152',9.635200000000001e-08], + ['Gd154',1.0502368e-06], + ['Gd155',7.130048e-06], + ['Gd156',9.8616272e-06], + ['Gd157',7.539543999999999e-06], + ['Gd158',1.1966918400000001e-05], + ['Gd160',1.05312736e-05], + ['H1',0.04897300000000001], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=63.197, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-13.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-13.py new file mode 100644 index 0000000..5127586 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-13.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4252e-07], + ['Gd152',1.1910000000000001e-07], + ['Gd154',1.2981899999999998e-06], + ['Gd155',8.8134e-06], + ['Gd156',1.2189884999999999e-05], + ['Gd157',9.319575e-06], + ['Gd158',1.4792220000000002e-05], + ['Gd160',1.301763e-05], + ['H1',0.048973], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=68.937, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-14.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-14.py new file mode 100644 index 0000000..6134691 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-14.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4252e-07], + ['Gd152',1.40928e-07], + ['Gd154',1.5361151999999999e-06], + ['Gd155',1.0428671999999999e-05], + ['Gd156',1.44239808e-05], + ['Gd157',1.1027616e-05], + ['Gd158',1.75032576e-05], + ['Gd160',1.5403430399999997e-05], + ['H1',0.048972999999999996], + ['N14',0.006136041048200001], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=75.877, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-15.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-15.py new file mode 100644 index 0000000..64f5268 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-15.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4252e-07], + ['Gd152',1.55098e-07], + ['Gd154',1.6905682e-06], + ['Gd155',1.1477252e-05], + ['Gd156',1.5874280299999998e-05], + ['Gd157',1.2136418499999998e-05], + ['Gd158',1.92631716e-05], + ['Gd160',1.69522114e-05], + ['H1',0.048973], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=81.537, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-2.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-2.py new file mode 100644 index 0000000..9e6ef13 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-2.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.2912e-07], + ['Pu239',0.00026498], + ['Pu240',2.4383e-05], + ['Pu242',1.4141e-07], + ['Gd152',3.6764000000000002e-09], + ['Gd154',4.007276e-08], + ['Gd155',2.720536e-07], + ['Gd156',3.7627954e-07], + ['Gd157',2.876783e-07], + ['Gd158',4.5660888e-07], + ['Gd160',4.0183051999999997e-07], + ['H1',0.06097299999999999], + ['N14',0.0023118007411], + ['N15',8.4992589e-06], + ['O16',0.03687601869], + ['O17',1.398131e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=42.337, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-3.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-3.py new file mode 100644 index 0000000..e5f9b2a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-3.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.2912e-07], + ['Pu239',0.00026498], + ['Pu240',2.4383e-05], + ['Pu242',1.4141e-07], + ['Gd152',7.3528000000000005e-09], + ['Gd154',8.014552e-08], + ['Gd155',5.441072e-07], + ['Gd156',7.5255908e-07], + ['Gd157',5.753566e-07], + ['Gd158',9.132177599999999e-07], + ['Gd160',8.036610399999999e-07], + ['H1',0.060973], + ['N14',0.0023118007411], + ['N15',8.4992589e-06], + ['O16',0.03687601869], + ['O17',1.3981309999999998e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=48.157, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-4.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-4.py new file mode 100644 index 0000000..2622aa2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-4.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.2912e-07], + ['Pu239',0.00026498], + ['Pu240',2.4383e-05], + ['Pu242',1.4141e-07], + ['Gd152',1.0876000000000001e-08], + ['Gd154',1.1854839999999999e-07], + ['Gd155',8.048239999999999e-07], + ['Gd156',1.1131586e-06], + ['Gd157',8.510469999999999e-07], + ['Gd158',1.3507992000000001e-06], + ['Gd160',1.1887468e-06], + ['H1',0.060973], + ['N14',0.0023118007411], + ['N15',8.4992589e-06], + ['O16',0.03687601869], + ['O17',1.398131e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=56.657, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-5.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-5.py new file mode 100644 index 0000000..a1355a3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-5.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.2912e-07], + ['Pu239',0.00026498], + ['Pu240',2.4383e-05], + ['Pu242',1.4141e-07], + ['Gd152',1.47056e-08], + ['Gd154',1.6029104e-07], + ['Gd155',1.0882144e-06], + ['Gd156',1.50511816e-06], + ['Gd157',1.1507132e-06], + ['Gd158',1.8264355199999999e-06], + ['Gd160',1.6073220799999999e-06], + ['H1',0.060973000000000006], + ['N14',0.0023118007411], + ['N15',8.4992589e-06], + ['O16',0.03687601869], + ['O17',1.398131e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=70.457, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-6.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-6.py new file mode 100644 index 0000000..cf5b450 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-6.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',1.2912e-07], + ['Pu239',0.00026498], + ['Pu240',2.4383e-05], + ['Pu242',1.4141e-07], + ['Gd152',1.82288e-08], + ['Gd154',1.9869392e-07], + ['Gd155',1.3489312e-06], + ['Gd156',1.86571768e-06], + ['Gd157',1.4264036000000002e-06], + ['Gd158',2.2640169600000004e-06], + ['Gd160',1.99240784e-06], + ['H1',0.060973], + ['N14',0.0023118007411], + ['N15',8.4992589e-06], + ['O16',0.03687601869], + ['O17',1.3981309999999998e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=102.547, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-7.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-7.py new file mode 100644 index 0000000..9291692 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-7.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008291999999999999], + ['Pu240',7.6302e-05], + ['Pu242',4.4251999999999997e-07], + ['Gd152',3.37e-08], + ['Gd154',3.6733e-07], + ['Gd155',2.4937999999999997e-06], + ['Gd156',3.4491949999999996e-06], + ['Gd157',2.637025e-06], + ['Gd158',4.18554e-06], + ['Gd160',3.683409999999999e-06], + ['H1',0.048972999999999996], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=48.697, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-8.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-8.py new file mode 100644 index 0000000..5b50c13 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-8.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.425200000000001e-07], + ['Gd152',4.044e-08], + ['Gd154',4.4079599999999997e-07], + ['Gd155',2.9925599999999997e-06], + ['Gd156',4.139033999999999e-06], + ['Gd157',3.16443e-06], + ['Gd158',5.0226480000000005e-06], + ['Gd160',4.420092e-06], + ['H1',0.048973], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=50.247, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-9.py b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-9.py new file mode 100644 index 0000000..d20ffd4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/mcdc/pu-sol-therm-034_case-9.py @@ -0,0 +1,102 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: fissile solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['Pu238',4.0405e-07], + ['Pu239',0.0008292], + ['Pu240',7.6302e-05], + ['Pu242',4.4252e-07], + ['Gd152',4.81e-08], + ['Gd154',5.242899999999999e-07], + ['Gd155',3.5593999999999998e-06], + ['Gd156',4.923034999999999e-06], + ['Gd157',3.763825e-06], + ['Gd158',5.97402e-06], + ['Gd160',5.257329999999999e-06], + ['H1',0.048973], + ['N14',0.0061360410482000005], + ['N15',2.25589518e-05], + ['O16',0.041712185088], + ['O17',1.5814912e-05]]) +# Material Name: 304L stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0036985991000000004], + ['Fe56',0.05806009612], + ['Fe57',0.0013408608200000001], + ['Fe58',0.00017844395999999998], + ['Cr50',0.0007183154000000001], + ['Cr52',0.01385199748], + ['Cr53',0.0015707053200000004], + ['Cr54',0.00039098180000000005], + ['Ni58',0.0044314658055], + ['Ni60',0.0017069926944999999], + ['Ni61',7.420179049999999e-05], + ['Ni62',0.0002365877775], + ['Ni64',6.0251932e-05]]) +# Material Name: Water at 23 C +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066691], + ['O16',0.033333361866], + ['O17',1.2638134e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s10 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.555, bc='interface') +s11 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=2.86, bc='interface') +s12 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.514, bc='interface') +s13 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=30.593, bc='interface') +s14 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.523, bc='interface') +s15 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=50.8, bc='vacuum') +s20 = mcdc.surface('plane-z', z=0.0, bc='vacuum') +s21 = mcdc.surface('plane-z', z=0.277, bc='interface') +s22 = mcdc.surface('plane-z', z=21.227, bc='interface') +s23 = mcdc.surface('plane-z', z=22.177, bc='interface') +s24 = mcdc.surface('plane-z', z=51.797, bc='interface') +s25 = mcdc.surface('plane-z', z=127.828, bc='interface') +s26 = mcdc.surface('plane-z', z=127.907, bc='interface') +s27 = mcdc.surface('plane-z', z=143.0, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s12 & +s23 & -s24, fill=m1) +c2 = mcdc.cell(+s10 & -s15 & +s20 & -s21, fill=m2) +c3 = mcdc.cell(+s10 & -s11 & +s21 & -s22, fill=m2) +c4 = mcdc.cell(-s13 & +s22 & -s23, fill=m2) +c5 = mcdc.cell(+s12 & -s13 & +s23 & -s25, fill=m2) +c6 = mcdc.cell(-s13 & +s25 & -s26, fill=m2) +c7 = mcdc.cell(+s14 & -s15 & +s21 & -s27, fill=m2) +c8 = mcdc.cell(+s11 & -s14 & +s21 & -s22, fill=m3) +c9 = mcdc.cell(+s13 & -s14 & +s22 & -s26, fill=m3) +c10 = mcdc.cell(-s10 & +s20 & -s22, fill=mvoid) +c11 = mcdc.cell(-s12 & +s24 & -s25, fill=mvoid) +c12 = mcdc.cell(-s14 & +s26 & -s27, fill=mvoid) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: point +mcdc.source(point=[0.0,0.0,0.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-1/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..d7bbd37 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/generate_materials.py @@ -0,0 +1,35 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.2912e-07) +mat.add_nuclide('Pu239', 2.6498e-04) +mat.add_nuclide('Pu240', 2.4383e-05) +mat.add_nuclide('Pu241', 2.4661e-06) +mat.add_nuclide('Pu242', 1.4141e-07) +mat.add_nuclide('H1', 6.0973e-02) +mat.add_element('N', 2.3203e-03) +mat.add_element('O', 3.6890e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-1/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/geometry.xml new file mode 100644 index 0000000..eab7bd3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-1/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/materials.xml new file mode 100644 index 0000000..cec0622 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/materials.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-1/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-1/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-10/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/generate_materials.py new file mode 100644 index 0000000..18d18b4 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 3.1441e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-10/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/geometry.xml new file mode 100644 index 0000000..c2f8830 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-10/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/materials.xml new file mode 100644 index 0000000..0d2f9fe --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-10/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-10/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-11/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/generate_materials.py new file mode 100644 index 0000000..01310b9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 3.7836e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-11/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/geometry.xml new file mode 100644 index 0000000..b1716c7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-11/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/materials.xml new file mode 100644 index 0000000..fb15203 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-11/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-11/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-12/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/generate_materials.py new file mode 100644 index 0000000..bd6acba --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 4.8176e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-12/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/geometry.xml new file mode 100644 index 0000000..37d8cb7 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-12/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/materials.xml new file mode 100644 index 0000000..94ebacb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-12/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-12/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-13/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/generate_materials.py new file mode 100644 index 0000000..e968768 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 5.9550e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-13/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/geometry.xml new file mode 100644 index 0000000..c5192e3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-13/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/materials.xml new file mode 100644 index 0000000..d78bee9 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-13/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-13/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-14/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/generate_materials.py new file mode 100644 index 0000000..a3559c3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 7.0464e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-14/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/geometry.xml new file mode 100644 index 0000000..dc76e48 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-14/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/materials.xml new file mode 100644 index 0000000..61146e2 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-14/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-14/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-15/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/generate_materials.py new file mode 100644 index 0000000..5c95190 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 7.7549e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-15/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/geometry.xml new file mode 100644 index 0000000..58736f3 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-15/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/materials.xml new file mode 100644 index 0000000..de1f920 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-15/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-15/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-2/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..d0f693c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.2912e-07) +mat.add_nuclide('Pu239', 2.6498e-04) +mat.add_nuclide('Pu240', 2.4383e-05) +mat.add_nuclide('Pu241', 2.4661e-06) +mat.add_nuclide('Pu242', 1.4141e-07) +mat.add_element('Gd', 1.8382e-06) +mat.add_nuclide('H1', 6.0973e-02) +mat.add_element('N', 2.3203e-03) +mat.add_element('O', 3.6890e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-2/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/geometry.xml new file mode 100644 index 0000000..2f3f5b5 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-2/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/materials.xml new file mode 100644 index 0000000..d6ac160 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-2/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-2/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-3/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..7bd3880 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.2912e-07) +mat.add_nuclide('Pu239', 2.6498e-04) +mat.add_nuclide('Pu240', 2.4383e-05) +mat.add_nuclide('Pu241', 2.4661e-06) +mat.add_nuclide('Pu242', 1.4141e-07) +mat.add_element('Gd', 3.6764e-06) +mat.add_nuclide('H1', 6.0973e-02) +mat.add_element('N', 2.3203e-03) +mat.add_element('O', 3.6890e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-3/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/geometry.xml new file mode 100644 index 0000000..000f34c --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-3/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/materials.xml new file mode 100644 index 0000000..d3e6c56 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-3/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-3/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-4/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..3a76835 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.2912e-07) +mat.add_nuclide('Pu239', 2.6498e-04) +mat.add_nuclide('Pu240', 2.4383e-05) +mat.add_nuclide('Pu241', 2.4661e-06) +mat.add_nuclide('Pu242', 1.4141e-07) +mat.add_element('Gd', 5.4380e-06) +mat.add_nuclide('H1', 6.0973e-02) +mat.add_element('N', 2.3203e-03) +mat.add_element('O', 3.6890e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-4/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/geometry.xml new file mode 100644 index 0000000..a247b67 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-4/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/materials.xml new file mode 100644 index 0000000..9adcb0a --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-4/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-4/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-5/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..8b49178 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.2912e-07) +mat.add_nuclide('Pu239', 2.6498e-04) +mat.add_nuclide('Pu240', 2.4383e-05) +mat.add_nuclide('Pu241', 2.4661e-06) +mat.add_nuclide('Pu242', 1.4141e-07) +mat.add_element('Gd', 7.3528e-06) +mat.add_nuclide('H1', 6.0973e-02) +mat.add_element('N', 2.3203e-03) +mat.add_element('O', 3.6890e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-5/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/geometry.xml new file mode 100644 index 0000000..1d0957b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-5/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/materials.xml new file mode 100644 index 0000000..dc2b349 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-5/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-5/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-6/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/generate_materials.py new file mode 100644 index 0000000..7105a86 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 1.2912e-07) +mat.add_nuclide('Pu239', 2.6498e-04) +mat.add_nuclide('Pu240', 2.4383e-05) +mat.add_nuclide('Pu241', 2.4661e-06) +mat.add_nuclide('Pu242', 1.4141e-07) +mat.add_element('Gd', 9.1144e-06) +mat.add_nuclide('H1', 6.0973e-02) +mat.add_element('N', 2.3203e-03) +mat.add_element('O', 3.6890e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-6/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/geometry.xml new file mode 100644 index 0000000..2799209 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-6/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/materials.xml new file mode 100644 index 0000000..7b09e5b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-6/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-6/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-7/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/generate_materials.py new file mode 100644 index 0000000..5019919 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 1.6850e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-7/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/geometry.xml new file mode 100644 index 0000000..5c4af94 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-7/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/materials.xml new file mode 100644 index 0000000..6a03a5b --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-7/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-7/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-8/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/generate_materials.py new file mode 100644 index 0000000..5c558fd --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 2.0220e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-8/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/geometry.xml new file mode 100644 index 0000000..5076fa0 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-8/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/materials.xml new file mode 100644 index 0000000..13d2bed --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-8/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-8/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-9/generate_materials.py b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/generate_materials.py new file mode 100644 index 0000000..ce27112 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/generate_materials.py @@ -0,0 +1,36 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "fissile solution" +mat.set_density('sum') +mat.add_nuclide('Pu238', 4.0405e-07) +mat.add_nuclide('Pu239', 8.2920e-04) +mat.add_nuclide('Pu240', 7.6302e-05) +mat.add_nuclide('Pu241', 7.7173e-06) +mat.add_nuclide('Pu242', 4.4252e-07) +mat.add_element('Gd', 2.4050e-05) +mat.add_nuclide('H1', 4.8973e-02) +mat.add_element('N', 6.1586e-03) +mat.add_element('O', 4.1728e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "304L stainless steel" +mat.set_density('sum') +mat.add_element('Fe', 6.3278e-02) +mat.add_element('Cr', 1.6532e-02) +mat.add_element('Ni', 6.5095e-03) +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water at 23 C" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6691e-02) +mat.add_element('O', 3.3346e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-9/geometry.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/geometry.xml new file mode 100644 index 0000000..98730e8 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/geometry.xml @@ -0,0 +1,40 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-9/materials.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/materials.xml new file mode 100644 index 0000000..0ed0beb --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/materials.xml @@ -0,0 +1,47 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/pu-sol-therm-034/openmc/case-9/settings.xml b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/settings.xml new file mode 100644 index 0000000..298ae59 --- /dev/null +++ b/icsbep/openmc/pu-sol-therm-034/openmc/case-9/settings.xml @@ -0,0 +1,15 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + + \ No newline at end of file diff --git a/icsbep/openmc/run_mcdc.sh b/icsbep/openmc/run_mcdc.sh new file mode 100755 index 0000000..ab7835f --- /dev/null +++ b/icsbep/openmc/run_mcdc.sh @@ -0,0 +1,41 @@ +#!/bin/bash + +# Get the root directory (the directory where the script is located) +ROOT_DIR="$(dirname "$(realpath "$0")")" + +# Find all directories named "mcdc" under the root directory +find "$ROOT_DIR" -type d -name "mcdc" | while read -r MCDC_DIR; do + echo "Processing directory: $MCDC_DIR" + cd "$MCDC_DIR" || continue # Change to the mcdc directory + rm *.log + + # Find all Python scripts inside the directory + find . -maxdepth 1 -type f -name "*.py" | while read -r PYTHON_SCRIPT; do + echo "Found Python script: $PYTHON_SCRIPT" + + # Create a Slurm batch script + JOB_SCRIPT="submit_job_$(basename "$PYTHON_SCRIPT" .py).sh" + cat > "$JOB_SCRIPT" < "$JOB_SCRIPT" </openmc/executable/bin/openmc > openmc.stdout 2>&1 +EOL + + # Submit the job + sbatch "$JOB_SCRIPT" + echo "Submitted job for $dir" + +done \ No newline at end of file diff --git a/icsbep/openmc/set_openmc_settings.py b/icsbep/openmc/set_openmc_settings.py new file mode 100644 index 0000000..de68c2c --- /dev/null +++ b/icsbep/openmc/set_openmc_settings.py @@ -0,0 +1,31 @@ +import os +import xml.etree.ElementTree as ET + +def update_settings_xml(xml_file): + try: + tree = ET.parse(xml_file) + root = tree.getroot() + + # Update values in settings.xml + for elem in root.findall("batches"): + elem.text = "200" + for elem in root.findall("inactive"): + elem.text = "20" + for elem in root.findall("particles"): + elem.text = "10000" + + # Write back changes + tree.write(xml_file, encoding="utf-8", xml_declaration=True) + print(f"Updated: {xml_file}") + except Exception as e: + print(f"Error updating {xml_file}: {e}") + +def find_and_update_settings(root_dir): + for dirpath, _, filenames in os.walk(root_dir): + for filename in filenames: + if filename == "settings.xml": + xml_path = os.path.join(dirpath, filename) + update_settings_xml(xml_path) + +root_directory = os.getcwd() # Start search from current directory +find_and_update_settings(root_directory) \ No newline at end of file diff --git a/icsbep/openmc/setup.py b/icsbep/openmc/setup.py new file mode 100644 index 0000000..24d5b2d --- /dev/null +++ b/icsbep/openmc/setup.py @@ -0,0 +1,11 @@ +#!/usr/bin/env python + +from setuptools import setup + +setup(name='icsbep', + version='0.1', + description='ICSBEP', + author='Paul Romano', + author_email='paul.k.romano@gmail.com', + packages=['icsbep'], + package_data={'icsbep': ['uncertainties.csv']}) diff --git a/icsbep/openmc/spec-met-fast-003/mcdc/spec-met-fast-003.py b/icsbep/openmc/spec-met-fast-003/mcdc/spec-met-fast-003.py new file mode 100644 index 0000000..0cbc6d9 --- /dev/null +++ b/icsbep/openmc/spec-met-fast-003/mcdc/spec-met-fast-003.py @@ -0,0 +1,62 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['Np237',0.051876]]) +m2 = mcdc.material(nuclides=[ + ['Ni58',0.062169186618], + ['Ni60',0.023947459382000002], + ['Ni61',0.0010409794779999999], + ['Ni62',0.0033190980900000004], + ['Ni64',0.0008452764320000001]]) +# Depletable +m3 = mcdc.material(nuclides=[ + ['U235',0.044482], + ['U238',0.0027038]]) +# Depletable +m4 = mcdc.material(nuclides=[ + ['U235',0.0003505], + ['U238',0.047717]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.6921, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.7062, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=0.7266, bc='interface') +s4 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.1156, bc='interface') +s5 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=24.1242, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=mvoid) +c4 = mcdc.cell(+s3 & -s4, fill=m3) +c5 = mcdc.cell(+s4 & -s5, fill=m4) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-25.0,25.0], y=[-25.0,25.0], z=[-25.0,25.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/spec-met-fast-003/openmc/generate_materials.py b/icsbep/openmc/spec-met-fast-003/openmc/generate_materials.py new file mode 100644 index 0000000..77ef656 --- /dev/null +++ b/icsbep/openmc/spec-met-fast-003/openmc/generate_materials.py @@ -0,0 +1,28 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('Np237', 5.1876e-2) +mats.append(mat) + +mat = openmc.Material(2) +mat.set_density('sum') +mat.add_element('Ni', 9.1322e-2) +mats.append(mat) + +mat = openmc.Material(3) +mat.set_density('sum') +mat.add_nuclide('U234', 4.8869e-4) +mat.add_nuclide('U235', 4.4482e-2) +mat.add_nuclide('U238', 2.7038e-3) +mats.append(mat) + +mat = openmc.Material(4) +mat.set_density('sum') +mat.add_nuclide('U235', 3.5050e-4) +mat.add_nuclide('U238', 4.7717e-2) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/spec-met-fast-003/openmc/geometry.xml b/icsbep/openmc/spec-met-fast-003/openmc/geometry.xml new file mode 100644 index 0000000..5d8d674 --- /dev/null +++ b/icsbep/openmc/spec-met-fast-003/openmc/geometry.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/spec-met-fast-003/openmc/materials.xml b/icsbep/openmc/spec-met-fast-003/openmc/materials.xml new file mode 100644 index 0000000..37516c3 --- /dev/null +++ b/icsbep/openmc/spec-met-fast-003/openmc/materials.xml @@ -0,0 +1,26 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/spec-met-fast-003/openmc/settings.xml b/icsbep/openmc/spec-met-fast-003/openmc/settings.xml new file mode 100644 index 0000000..9e50714 --- /dev/null +++ b/icsbep/openmc/spec-met-fast-003/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -25. -25. -25. 25. 25. 25. + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-comp-therm-001/mcdc/u233-comp-therm-001_case-3.py b/icsbep/openmc/u233-comp-therm-001/mcdc/u233-comp-therm-001_case-3.py new file mode 100644 index 0000000..52584ff --- /dev/null +++ b/icsbep/openmc/u233-comp-therm-001/mcdc/u233-comp-therm-001_case-3.py @@ -0,0 +1,188 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: Zircaloy-2 +m1 = mcdc.material(nuclides=[ + ['Zr90',0.0218852865], + ['Zr91',0.004772651399999999], + ['Zr92',0.007295095500000001], + ['Zr94',0.0073929306], + ['Zr96',0.001191036], + ['Sn112',4.842046e-06], + ['Sn114',3.2945879999999994e-06], + ['Sn115',1.697212e-06], + ['Sn116',7.2580772e-05], + ['Sn117',3.8337023999999995e-05], + ['Sn118',0.000120901396], + ['Sn119',4.2879562000000005e-05], + ['Sn120',0.000162632844], + ['Sn122',2.3112034000000005e-05], + ['Sn124',2.8902522e-05]]) +# Material Name: Polyethylene (0.9183 g/cm3) +# S(a,b): c_H_in_CH2 (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['H1',0.078854], + ['C0',0.039427]]) +# Material Name: Water (0.9982 g/cm3) +# S(a,b): c_H_in_H2O (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['H1',0.066735], + ['O16',0.033355353528], + ['O17',1.2646472000000002e-05]]) +# Material Name: Borated Steel +m4 = mcdc.material(nuclides=[ + ['Fe54',0.00346368855], + ['Fe56',0.054372502860000005], + ['Fe57',0.00125569821], + ['Fe58',0.00016711038], + ['Cr50',0.0007572466000000001], + ['Cr52',0.014602746919999998], + ['Cr53',0.0016558342799999999], + ['Cr54',0.00041217219999999994], + ['Mn55',0.00086816], + ['Ni58',0.0051174086499], + ['Ni60',0.0019712166501], + ['Ni61',8.56874229e-05], + ['Ni62',0.0002732089995], + ['Ni64',6.95782776e-05], + ['B10',0.0037488]]) +# Material Name: UO2-ZrO2 Seed Fuel (97.29 w/o U-233) +# Depletable +m5 = mcdc.material(nuclides=[ + ['U233',0.0039891], + ['U238',4.5759e-05], + ['O16',0.053911559771999996], + ['O17',2.0440228000000005e-05], + ['Zr90',0.011765071499999998], + ['Zr91',0.0025656774], + ['Zr92',0.0039216905], + ['Zr94',0.0039742846], + ['Zr96',0.0006402760000000001]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=42.18, bc='vacuum') +s2 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.26797, bc='interface') +s3 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.2794, bc='interface') +s4 = mcdc.surface('cylinder-z', center=[0.0, 0.0], radius=0.32385, bc='interface') +s5 = mcdc.surface('plane-z', z=-56.2991, bc='vacuum') +s6 = mcdc.surface('plane-z', z=-25.8191, bc='interface') +s7 = mcdc.surface('plane-z', z=-19.05, bc='interface') +s8 = mcdc.surface('plane-z', z=16.05, bc='interface') +s9 = mcdc.surface('plane-z', z=19.05, bc='interface') +s10 = mcdc.surface('plane-z', z=25.8191, bc='interface') +s11 = mcdc.surface('plane-z', z=56.2991, bc='vacuum') +s12 = mcdc.surface('plane-x', x=-8.27532, bc='interface') +s13 = mcdc.surface('plane-x', x=8.27532, bc='interface') +s14 = mcdc.surface('plane-y', y=-7.35584, bc='interface') +s15 = mcdc.surface('plane-y', y=7.35584, bc='interface') +s21 = mcdc.surface('plane-x', x=-0.37084, bc='interface') +s22 = mcdc.surface('plane-x', x=0.37084, bc='interface') +s23 = mcdc.surface('plane-y', y=-0.37084, bc='interface') +s24 = mcdc.surface('plane-y', y=0.37084, bc='interface') +s25 = mcdc.surface('plane-x', x=-3.81, bc='interface') +s26 = mcdc.surface('plane-x', x=3.81, bc='interface') +s27 = mcdc.surface('plane-y', y=-5.60578, bc='interface') +s28 = mcdc.surface('plane-y', y=-5.42798, bc='interface') +s29 = mcdc.surface('plane-y', y=-1.92786, bc='interface') +s30 = mcdc.surface('plane-y', y=-1.75006, bc='interface') +s31 = mcdc.surface('plane-y', y=1.75006, bc='interface') +s32 = mcdc.surface('plane-y', y=1.92786, bc='interface') +s33 = mcdc.surface('plane-y', y=5.42798, bc='interface') +s34 = mcdc.surface('plane-y', y=5.60578, bc='interface') + +# Material Cell(s) +c101 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c102 = mcdc.cell(-s2 & -s7, fill=m1) +c103 = mcdc.cell(-s2 & +s9, fill=m1) +c104 = mcdc.cell(+s2 & -s3, fill=mvoid) +c105 = mcdc.cell(+s3 & -s4, fill=m1) +c106 = mcdc.cell(+s4, fill=m3) +c201 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c202 = mcdc.cell(-s2 & -s7, fill=m1) +c203 = mcdc.cell(-s2 & +s9, fill=m1) +c204 = mcdc.cell(+s2 & -s3, fill=mvoid) +c205 = mcdc.cell(+s3 & -s4, fill=m1) +c206 = mcdc.cell(+s4 & -s8, fill=m3) +c207 = mcdc.cell(+s4 & +s8 & +s23, fill=m3) +c208 = mcdc.cell(+s8 & -s23, fill=m4) +c301 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c302 = mcdc.cell(-s2 & -s7, fill=m1) +c303 = mcdc.cell(-s2 & +s9, fill=m1) +c304 = mcdc.cell(+s2 & -s3, fill=mvoid) +c305 = mcdc.cell(+s3 & -s4, fill=m1) +c306 = mcdc.cell(+s4 & -s8, fill=m3) +c307 = mcdc.cell(+s4 & +s8 & -s24, fill=m3) +c308 = mcdc.cell(+s8 & +s24, fill=m4) +c401 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c402 = mcdc.cell(-s2 & -s7, fill=m1) +c403 = mcdc.cell(-s2 & +s9, fill=m1) +c404 = mcdc.cell(+s2 & -s3, fill=mvoid) +c405 = mcdc.cell(+s3 & -s4, fill=m1) +c406 = mcdc.cell(+s4 & -s8, fill=m3) +c407 = mcdc.cell(+s4 & +s8 & +s23, fill=m3) +c408 = mcdc.cell(+s4 & +s8 & -s23 & -s22, fill=m3) +c409 = mcdc.cell(+s8 & -s23 & +s22, fill=m4) +c501 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c502 = mcdc.cell(-s2 & -s7, fill=m1) +c503 = mcdc.cell(-s2 & +s9, fill=m1) +c504 = mcdc.cell(+s2 & -s3, fill=mvoid) +c505 = mcdc.cell(+s3 & -s4, fill=m1) +c506 = mcdc.cell(+s4 & -s8, fill=m3) +c507 = mcdc.cell(+s4 & +s8 & +s23, fill=m3) +c508 = mcdc.cell(+s4 & +s8 & -s23 & +s21, fill=m3) +c509 = mcdc.cell(+s8 & -s23 & -s21, fill=m4) +c601 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c602 = mcdc.cell(-s2 & -s7, fill=m1) +c603 = mcdc.cell(-s2 & +s9, fill=m1) +c604 = mcdc.cell(+s2 & -s3, fill=mvoid) +c605 = mcdc.cell(+s3 & -s4, fill=m1) +c606 = mcdc.cell(+s4 & -s8, fill=m3) +c607 = mcdc.cell(+s4 & +s8 & -s24, fill=m3) +c608 = mcdc.cell(+s4 & +s8 & +s24 & -s22, fill=m3) +c609 = mcdc.cell(+s8 & +s24 & +s22, fill=m4) +c701 = mcdc.cell(-s2 & +s7 & -s9, fill=m5) +c702 = mcdc.cell(-s2 & -s7, fill=m1) +c703 = mcdc.cell(-s2 & +s9, fill=m1) +c704 = mcdc.cell(+s2 & -s3, fill=mvoid) +c705 = mcdc.cell(+s3 & -s4, fill=m1) +c706 = mcdc.cell(+s4 & -s8, fill=m3) +c707 = mcdc.cell(+s4 & +s8 & -s24, fill=m3) +c708 = mcdc.cell(+s4 & +s8 & +s24 & +s21, fill=m3) +c709 = mcdc.cell(+s8 & +s24 & -s21, fill=m4) +c7 = mcdc.cell(+s10 & -s11 & +s25 & -s26 & +s27 & -s28, fill=m4) +c8 = mcdc.cell(+s10 & -s11 & +s25 & -s26 & +s29 & -s30, fill=m4) +c9 = mcdc.cell(+s10 & -s11 & +s25 & -s26 & +s31 & -s32, fill=m4) +c10 = mcdc.cell(+s10 & -s11 & +s25 & -s26 & +s33 & -s34, fill=m4) +c14 = mcdc.cell(-s1 & +s5 & -s6, fill=m3) +c15 = mcdc.cell(-s1 & +s6 & -s10 & -s12, fill=m3) +c16 = mcdc.cell(-s1 & +s6 & -s10 & +s13, fill=m3) +c17 = mcdc.cell(-s1 & +s6 & -s10 & +s12 & -s13 & -s14, fill=m3) +c18 = mcdc.cell(-s1 & +s6 & -s10 & +s12 & -s13 & +s15, fill=m3) +c19 = mcdc.cell(-s1 & +s10 & -s11 & -s27, fill=m3) +c20 = mcdc.cell(-s1 & +s10 & -s11 & +s27 & -s28 & -s25, fill=m3) +c21 = mcdc.cell(-s1 & +s10 & -s11 & +s27 & -s28 & +s26, fill=m3) +c22 = mcdc.cell(-s1 & +s10 & -s11 & +s28 & -s29, fill=m3) +c23 = mcdc.cell(-s1 & +s10 & -s11 & +s29 & -s30 & -s25, fill=m3) +c24 = mcdc.cell(-s1 & +s10 & -s11 & +s29 & -s30 & +s26, fill=m3) +c25 = mcdc.cell(-s1 & +s10 & -s11 & +s30 & -s31, fill=m3) +c26 = mcdc.cell(-s1 & +s10 & -s11 & +s31 & -s32 & -s25, fill=m3) +c27 = mcdc.cell(-s1 & +s10 & -s11 & +s31 & -s32 & +s26, fill=m3) +c28 = mcdc.cell(-s1 & +s10 & -s11 & +s32 & -s33, fill=m3) +c29 = mcdc.cell(-s1 & +s10 & -s11 & +s33 & -s34 & -s25, fill=m3) +c30 = mcdc.cell(-s1 & +s10 & -s11 & +s33 & -s34 & +s26, fill=m3) +c31 = mcdc.cell(-s1 & +s10 & -s11 & +s34, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +# Rectangular Lattice 100 +Lattice100 = mcdc.lattice(x=[-8.27532, 0.91948, 18], y=[-7.35584, 0.91948, 16], \ No newline at end of file diff --git a/icsbep/openmc/u233-comp-therm-001/openmc/case-3/generate_materials.py b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..6d562f2 --- /dev/null +++ b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/generate_materials.py @@ -0,0 +1,48 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "Zircaloy-2" +mat.set_density('sum') +mat.add_element('Zr', 4.2537e-02) +mat.add_element('Sn', 4.9918e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Polyethylene (0.9183 g/cm3)" +mat.set_density('sum') +mat.add_nuclide('H1', 7.8854e-02) +mat.add_element('C', 3.9427e-02) +mat.add_s_alpha_beta('c_H_in_CH2') +mats.append(mat) + +mat = openmc.Material(3) +mat.name = "Water (0.9982 g/cm3)" +mat.set_density('sum') +mat.add_nuclide('H1', 6.6735e-02) +mat.add_element('O', 3.3368e-02) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(4) +mat.name = "Borated Steel" +mat.set_density('sum') +mat.add_element('Fe', 5.9259e-02) +mat.add_element('Cr', 1.7428e-02) +mat.add_element('Mn', 8.6816e-04) +mat.add_element('Ni', 7.5171e-03) +mat.add_nuclide('B10', 3.7488e-03) +mats.append(mat) + +mat = openmc.Material(5) +mat.name = "UO2-ZrO2 Seed Fuel (97.29 w/o U-233)" +mat.set_density('sum') +mat.add_nuclide('U233', 3.9891e-03) +mat.add_nuclide('U234', 6.3690e-05) +mat.add_nuclide('U238', 4.5759e-05) +mat.add_element('O', 5.3932e-02) +mat.add_element('Zr', 2.2867e-02) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-comp-therm-001/openmc/case-3/geometry.xml b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/geometry.xml new file mode 100644 index 0000000..b513dbd --- /dev/null +++ b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/geometry.xml @@ -0,0 +1,173 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + 18 16 + -8.27532 -7.35584 + 0.91948 0.91948 + + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 4 2 2 2 2 2 2 2 2 5 1 1 1 1 + 1 1 1 1 6 3 3 3 3 3 3 3 3 7 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 4 2 2 2 2 2 2 2 2 5 1 1 1 1 + 1 1 1 1 6 3 3 3 3 3 3 3 3 7 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 4 2 2 2 2 2 2 2 2 5 1 1 1 1 + 1 1 1 1 6 3 3 3 3 3 3 3 3 7 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + 1 1 1 1 4 2 2 2 2 2 2 2 2 5 1 1 1 1 + 1 1 1 1 6 3 3 3 3 3 3 3 3 7 1 1 1 1 + 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-comp-therm-001/openmc/case-3/materials.xml b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/materials.xml new file mode 100644 index 0000000..7987be3 --- /dev/null +++ b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/materials.xml @@ -0,0 +1,65 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-comp-therm-001/openmc/case-3/plots.xml b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/plots.xml new file mode 100644 index 0000000..e1618c5 --- /dev/null +++ b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/plots.xml @@ -0,0 +1,35 @@ + + + + + + + xy + 0. 0. 0. + 20. 20. + 2000 2000 + + + + xy + 0. 0. 18. + 20. 20. + 2000 2000 + + + + xy + 0. 0. 30. + 20. 20. + 2000 2000 + + + + diff --git a/icsbep/openmc/u233-comp-therm-001/openmc/case-3/settings.xml b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/settings.xml new file mode 100644 index 0000000..cda497f --- /dev/null +++ b/icsbep/openmc/u233-comp-therm-001/openmc/case-3/settings.xml @@ -0,0 +1,20 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + + -8.27532 -7.35584 -25.8191 + 8.27532 7.35584 25.8191 + + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-001/mcdc/u233-met-fast-001.py b/icsbep/openmc/u233-met-fast-001/mcdc/u233-met-fast-001.py new file mode 100644 index 0000000..2492666 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-001/mcdc/u233-met-fast-001.py @@ -0,0 +1,18 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U233',0.046712], + ['U235',1.4281000000000001e-05], + ['U238',0.00028561]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) diff --git a/icsbep/openmc/u233-met-fast-001/openmc/geometry.xml b/icsbep/openmc/u233-met-fast-001/openmc/geometry.xml new file mode 100644 index 0000000..804d168 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-001/openmc/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + sphere + 0. 0. 0. 5.9838 + vacuum + + + diff --git a/icsbep/openmc/u233-met-fast-001/openmc/materials.xml b/icsbep/openmc/u233-met-fast-001/openmc/materials.xml new file mode 100644 index 0000000..82475f8 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-001/openmc/materials.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-001/openmc/settings.xml b/icsbep/openmc/u233-met-fast-001/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-001/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-002/mcdc/u233-met-fast-002_case-1.py b/icsbep/openmc/u233-met-fast-002/mcdc/u233-met-fast-002_case-1.py new file mode 100644 index 0000000..57d3ad3 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/mcdc/u233-met-fast-002_case-1.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U233',0.047253], + ['U238',0.00032975]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.044892], + ['U238',0.003234]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0444, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.2661, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-002/mcdc/u233-met-fast-002_case-2.py b/icsbep/openmc/u233-met-fast-002/mcdc/u233-met-fast-002_case-2.py new file mode 100644 index 0000000..b293d8d --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/mcdc/u233-met-fast-002_case-2.py @@ -0,0 +1,50 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: U233 Inner Sphere +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',0.047312], + ['U235',0.0005277], + ['U238',0.00033015]]) +# Material Name: U235 Outer Shell +# Depletable +m2 = mcdc.material(nuclides=[ + ['U235',0.044892], + ['U238',0.003234]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.5999, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=6.5887, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-1/geometry.xml b/icsbep/openmc/u233-met-fast-002/openmc/case-1/geometry.xml new file mode 100644 index 0000000..7390a06 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-1/materials.xml b/icsbep/openmc/u233-met-fast-002/openmc/case-1/materials.xml new file mode 100644 index 0000000..4e10823 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-1/materials.xml @@ -0,0 +1,24 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-1/settings.xml b/icsbep/openmc/u233-met-fast-002/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-2/generate_materials.py b/icsbep/openmc/u233-met-fast-002/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..9fd8d11 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-2/generate_materials.py @@ -0,0 +1,13 @@ +import openmc + +inner = openmc.Material(name="U233 Inner Sphere") +inner.add_nuclide('U233', 4.7312e-02) +inner.add_nuclide('U235', 5.2770e-04) +inner.add_nuclide('U238', 3.3015e-04) + +outer = openmc.Material(name = "U235 Outer Shell") +outer.add_nuclide('U235', 4.4892e-02) +outer.add_nuclide('U238', 3.2340e-03) + +materials = openmc.Materials([inner, outer]) +materials.export_to_xml() diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-2/geometry.xml b/icsbep/openmc/u233-met-fast-002/openmc/case-2/geometry.xml new file mode 100644 index 0000000..6b0c332 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-2/materials.xml b/icsbep/openmc/u233-met-fast-002/openmc/case-2/materials.xml new file mode 100644 index 0000000..2c11390 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-2/materials.xml @@ -0,0 +1,14 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-002/openmc/case-2/settings.xml b/icsbep/openmc/u233-met-fast-002/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-002/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-003/mcdc/u233-met-fast-003_case-1.py b/icsbep/openmc/u233-met-fast-003/mcdc/u233-met-fast-003_case-1.py new file mode 100644 index 0000000..4751314 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/mcdc/u233-met-fast-003_case-1.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U233',0.047253], + ['U238',0.00032975]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034902], + ['U238',0.047518]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0444, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.3456, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-003/mcdc/u233-met-fast-003_case-2.py b/icsbep/openmc/u233-met-fast-003/mcdc/u233-met-fast-003_case-2.py new file mode 100644 index 0000000..ddf28eb --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/mcdc/u233-met-fast-003_case-2.py @@ -0,0 +1,45 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U233',0.047312], + ['U238',0.00033015]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.00034902], + ['U238',0.047518]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.5999, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=9.9085, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-003/openmc/case-1/geometry.xml b/icsbep/openmc/u233-met-fast-003/openmc/case-1/geometry.xml new file mode 100644 index 0000000..6946d54 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-003/openmc/case-1/materials.xml b/icsbep/openmc/u233-met-fast-003/openmc/case-1/materials.xml new file mode 100644 index 0000000..1fb6673 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/openmc/case-1/materials.xml @@ -0,0 +1,24 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-003/openmc/case-1/settings.xml b/icsbep/openmc/u233-met-fast-003/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-003/openmc/case-2/geometry.xml b/icsbep/openmc/u233-met-fast-003/openmc/case-2/geometry.xml new file mode 100644 index 0000000..796131e --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-003/openmc/case-2/materials.xml b/icsbep/openmc/u233-met-fast-003/openmc/case-2/materials.xml new file mode 100644 index 0000000..287203c --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/openmc/case-2/materials.xml @@ -0,0 +1,24 @@ + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-003/openmc/case-2/settings.xml b/icsbep/openmc/u233-met-fast-003/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-003/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-004/mcdc/u233-met-fast-004_case-1.py b/icsbep/openmc/u233-met-fast-004/mcdc/u233-met-fast-004_case-1.py new file mode 100644 index 0000000..32bd5a9 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/mcdc/u233-met-fast-004_case-1.py @@ -0,0 +1,62 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',0.047253], + ['U238',0.00032975]]) +# Material Name: Tungsten reflector +m2 = mcdc.material(nuclides=[ + ['W180',6.17616e-05], + ['W182',0.01363902], + ['W183',0.0073650708], + ['W184',0.0157697952], + ['W186',0.0146323524], + ['Ni58',0.006611900835599999], + ['Ni60',0.0025468923643999996], + ['Ni61',0.00011071164759999998], + ['Ni62',0.000352997178], + ['Ni64',8.98979744e-05], + ['Cu63',0.0028195221], + ['Cu65',0.0012578779000000002], + ['Zr90',0.00040917155999999993], + ['Zr91',8.923041599999999e-05], + ['Zr92',0.00013639052], + ['Zr94',0.000138219664], + ['Zr96',2.226784e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0444, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.4828, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-004/mcdc/u233-met-fast-004_case-2.py b/icsbep/openmc/u233-met-fast-004/mcdc/u233-met-fast-004_case-2.py new file mode 100644 index 0000000..2ddb83e --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/mcdc/u233-met-fast-004_case-2.py @@ -0,0 +1,62 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',0.047312], + ['U238',0.00033015]]) +# Material Name: Tungsten reflector +m2 = mcdc.material(nuclides=[ + ['W180',6.17616e-05], + ['W182',0.01363902], + ['W183',0.0073650708], + ['W184',0.0157697952], + ['W186',0.0146323524], + ['Ni58',0.006611900835599999], + ['Ni60',0.0025468923643999996], + ['Ni61',0.00011071164759999998], + ['Ni62',0.000352997178], + ['Ni64',8.98979744e-05], + ['Cu63',0.0028195221], + ['Cu65',0.0012578779000000002], + ['Zr90',0.00040917155999999993], + ['Zr91',8.923041599999999e-05], + ['Zr92',0.00013639052], + ['Zr94',0.000138219664], + ['Zr96',2.226784e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.5999, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=10.3911, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-1/generate_materials.py b/icsbep/openmc/u233-met-fast-004/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..2ab84ce --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-1/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('U233', 4.7253e-2) +mat.add_nuclide('U234', 5.2705e-4) +mat.add_nuclide('U238', 3.2975e-4) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Tungsten reflector" +mat.set_density('sum') +mat.add_element('W', 5.1468e-02) +mat.add_element('Ni', 9.7124e-03) +mat.add_element('Cu', 4.0774e-03) +mat.add_element('Zr', 7.9528e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-1/geometry.xml b/icsbep/openmc/u233-met-fast-004/openmc/case-1/geometry.xml new file mode 100644 index 0000000..d638449 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-1/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-1/materials.xml b/icsbep/openmc/u233-met-fast-004/openmc/case-1/materials.xml new file mode 100644 index 0000000..777dd49 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-1/materials.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-1/settings.xml b/icsbep/openmc/u233-met-fast-004/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-2/generate_materials.py b/icsbep/openmc/u233-met-fast-004/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..890e702 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-2/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.set_density('sum') +mat.add_nuclide('U233', 4.7312e-2) +mat.add_nuclide('U234', 5.2770e-4) +mat.add_nuclide('U238', 3.3015e-4) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Tungsten reflector" +mat.set_density('sum') +mat.add_element('W', 5.1468e-02) +mat.add_element('Ni', 9.7124e-03) +mat.add_element('Cu', 4.0774e-03) +mat.add_element('Zr', 7.9528e-04) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-2/geometry.xml b/icsbep/openmc/u233-met-fast-004/openmc/case-2/geometry.xml new file mode 100644 index 0000000..11c14e1 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-2/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-2/materials.xml b/icsbep/openmc/u233-met-fast-004/openmc/case-2/materials.xml new file mode 100644 index 0000000..2242f29 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-2/materials.xml @@ -0,0 +1,29 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-004/openmc/case-2/settings.xml b/icsbep/openmc/u233-met-fast-004/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-004/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-005/mcdc/u233-met-fast-005_case-1.py b/icsbep/openmc/u233-met-fast-005/mcdc/u233-met-fast-005_case-1.py new file mode 100644 index 0000000..9809698 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/mcdc/u233-met-fast-005_case-1.py @@ -0,0 +1,50 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: U233 core +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',0.047253], + ['U238',0.00032975]]) +# Material Name: Beryllium reflector +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.11984], + ['O16',0.0013770778896], + ['O17',5.221104000000001e-07]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=5.0444, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.0891, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-005/mcdc/u233-met-fast-005_case-2.py b/icsbep/openmc/u233-met-fast-005/mcdc/u233-met-fast-005_case-2.py new file mode 100644 index 0000000..7b6e9f9 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/mcdc/u233-met-fast-005_case-2.py @@ -0,0 +1,50 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: U233 core +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',0.047312], + ['U238',0.00033015]]) +# Material Name: Beryllium reflector +# S(a,b): c_Be (Not Implemented) +m2 = mcdc.material(nuclides=[ + ['Be9',0.11984], + ['O16',0.0013770778896], + ['O17',5.221104000000001e-07]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.5999, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=8.796, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-1/generate_materials.py b/icsbep/openmc/u233-met-fast-005/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..a20a537 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-1/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "U233 core" +mat.set_density('sum') +mat.add_nuclide('U233', 4.7253e-02) +mat.add_nuclide('U234', 5.2705e-04) +mat.add_nuclide('U238', 3.2975e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Beryllium reflector" +mat.set_density('sum') +mat.add_element('Be', 1.1984e-01) +mat.add_element('O', 1.3776e-03) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-1/geometry.xml b/icsbep/openmc/u233-met-fast-005/openmc/case-1/geometry.xml new file mode 100644 index 0000000..10b8840 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-1/materials.xml b/icsbep/openmc/u233-met-fast-005/openmc/case-1/materials.xml new file mode 100644 index 0000000..f130bff --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-1/materials.xml @@ -0,0 +1,16 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-1/settings.xml b/icsbep/openmc/u233-met-fast-005/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-2/generate_materials.py b/icsbep/openmc/u233-met-fast-005/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..9363d2b --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-2/generate_materials.py @@ -0,0 +1,21 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "U233 core" +mat.set_density('sum') +mat.add_nuclide('U233', 4.7312e-02) +mat.add_nuclide('U234', 5.2770e-04) +mat.add_nuclide('U238', 3.3015e-04) +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Beryllium reflector" +mat.set_density('sum') +mat.add_element('Be', 1.1984e-01) +mat.add_element('O', 1.3776e-03) +mat.add_s_alpha_beta('c_Be') +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-2/geometry.xml b/icsbep/openmc/u233-met-fast-005/openmc/case-2/geometry.xml new file mode 100644 index 0000000..2411f61 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-2/materials.xml b/icsbep/openmc/u233-met-fast-005/openmc/case-2/materials.xml new file mode 100644 index 0000000..204cb04 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-2/materials.xml @@ -0,0 +1,16 @@ + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-005/openmc/case-2/settings.xml b/icsbep/openmc/u233-met-fast-005/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-005/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-met-fast-006/mcdc/u233-met-fast-006.py b/icsbep/openmc/u233-met-fast-006/mcdc/u233-met-fast-006.py new file mode 100644 index 0000000..ac75db8 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-006/mcdc/u233-met-fast-006.py @@ -0,0 +1,46 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +m1 = mcdc.material(nuclides=[ + ['U233',0.04671], + ['U235',1.4158e-05], + ['U238',0.00027959]]) +m2 = mcdc.material(nuclides=[ + ['U235',0.0003505], + ['U238',0.047719]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=4.2058, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=24.1194, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-met-fast-006/openmc/geometry.xml b/icsbep/openmc/u233-met-fast-006/openmc/geometry.xml new file mode 100644 index 0000000..efd55f7 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-006/openmc/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-006/openmc/materials.xml b/icsbep/openmc/u233-met-fast-006/openmc/materials.xml new file mode 100644 index 0000000..f28e702 --- /dev/null +++ b/icsbep/openmc/u233-met-fast-006/openmc/materials.xml @@ -0,0 +1,25 @@ + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-met-fast-006/openmc/settings.xml b/icsbep/openmc/u233-met-fast-006/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-met-fast-006/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-inter-001/mcdc/u233-sol-inter-001_case-1.py b/icsbep/openmc/u233-sol-inter-001/mcdc/u233-sol-inter-001_case-1.py new file mode 100644 index 0000000..989b6a3 --- /dev/null +++ b/icsbep/openmc/u233-sol-inter-001/mcdc/u233-sol-inter-001_case-1.py @@ -0,0 +1,72 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: IEU Flouride Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U232',4.5608e-08], + ['U233',0.0022379], + ['U235',8.959799999999998e-07], + ['U238',7.1284e-06], + ['H1',0.055183], + ['O16',0.032030855703], + ['O17',1.2144297e-05], + ['F19',0.0047182]]) +# Material Name: 347 Stainless steel +m2 = mcdc.material(nuclides=[ + ['Fe54',0.0035799456], + ['Fe56',0.05619748991999999], + ['Fe57',0.00129784512], + ['Fe58',0.00017271936], + ['Cr50',0.0007246590999999999], + ['Cr52',0.013974329419999999], + ['Cr53',0.0015845767799999998], + ['Cr54',0.00039443469999999995], + ['Ni58',0.0061448933016], + ['Ni60',0.0023670018984], + ['Ni61',0.0001028919336], + ['Ni62',0.000328064508], + ['Ni64',8.35483584e-05]]) +# Material Name: Beryllium reflector +# S(a,b): c_Be (Not Implemented) +m3 = mcdc.material(nuclides=[ + ['Be9',0.12161]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.8726, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=7.9209, bc='interface') +s3 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=15.9209, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +c3 = mcdc.cell(+s2 & -s3, fill=m3) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-inter-001/openmc/case-1/generate_materials.py b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..eafb051 --- /dev/null +++ b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/generate_materials.py @@ -0,0 +1,24 @@ +import openmc + +solution = openmc.Material(name="IEU Flouride Solution") +solution.add_nuclide('U232', 4.5608e-08) +solution.add_nuclide('U233', 2.2379e-03) +solution.add_nuclide('U234', 2.4316e-05) +solution.add_nuclide('U235', 8.9598e-07) +solution.add_nuclide('U238', 7.1284e-06) +solution.add_nuclide('H1', 5.5183e-02) +solution.add_element('O', 3.2043e-02) +solution.add_element('F', 4.7182e-03) +solution.add_s_alpha_beta('c_H_in_H2O') + +steel = openmc.Material(name="347 Stainless steel") +steel.add_element('Fe', 6.1248e-02) +steel.add_element('Cr', 1.6678e-02) +steel.add_element('Ni', 9.0264e-03) + +reflector = openmc.Material(name="Beryllium reflector") +reflector.add_element('Be', 1.2161e-01) +reflector.add_s_alpha_beta('c_Be') + +materials = openmc.Materials([solution, steel, reflector]) +materials.export_to_xml() diff --git a/icsbep/openmc/u233-sol-inter-001/openmc/case-1/geometry.xml b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/geometry.xml new file mode 100644 index 0000000..1596fe6 --- /dev/null +++ b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/geometry.xml @@ -0,0 +1,21 @@ + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-inter-001/openmc/case-1/materials.xml b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/materials.xml new file mode 100644 index 0000000..01f4719 --- /dev/null +++ b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/materials.xml @@ -0,0 +1,37 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-inter-001/openmc/case-1/settings.xml b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-inter-001/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-1.py b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-1.py new file mode 100644 index 0000000..a0c86f4 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-1.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2(NO3)2 Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',4.3271e-05], + ['U235',1.7565e-08], + ['U238',2.7748e-07], + ['N14',0.00011819000000000002], + ['H1',0.066271], + ['O16',0.033551279244], + ['O17',1.2720755999999998e-05], +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.595, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.915, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-2.py b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-2.py new file mode 100644 index 0000000..c05e2ea --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-2.py @@ -0,0 +1,65 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2(NO3)2 Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',4.5093e-05], + ['U235',1.8305e-08], + ['U238',2.8917e-07], + ['N14',0.00012248], + ['H1',0.066362], + ['O16',0.033615254988], + ['O17',1.2745011999999999e-05], + ['B10',2.6481e-07], + ['B11',1.0659e-06], +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.595, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.915, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-3.py b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-3.py new file mode 100644 index 0000000..e68dcf5 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-3.py @@ -0,0 +1,65 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2(NO3)2 Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',4.6768e-05], + ['U235',1.8984e-08], + ['U238',2.9991e-07], + ['N14',0.00012772], + ['H1',0.066413], + ['O16',0.033661237554], + ['O17',1.2762445999999999e-05], + ['B10',5.1591e-07], + ['B11',2.0766e-06], +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.595, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.915, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-4.py b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-4.py new file mode 100644 index 0000000..ba58c21 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-4.py @@ -0,0 +1,65 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2(NO3)2 Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',4.8433e-05], + ['U235',1.966e-08], + ['U238',3.1059e-07], + ['N14',0.00013173], + ['H1',0.066337], + ['O16',0.033640245513], + ['O17',1.2754487e-05], + ['B10',7.6312e-07], + ['B11',3.0716e-06], +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.595, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.915, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-5.py b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-5.py new file mode 100644 index 0000000..98ef69c --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/mcdc/u233-sol-therm-001_case-5.py @@ -0,0 +1,65 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2(NO3)2 Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',5.0042999999999995e-05], + ['U235',2.0314e-08], + ['U238',3.2091e-07], + ['N14',0.00013586], + ['H1',0.066329], + ['O16',0.033653240586], + ['O17',1.2759414e-05], + ['B10',1.0114e-06], + ['B11',4.0708e-06], +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.595, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=34.915, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-1/generate_materials.py b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/generate_materials.py new file mode 100644 index 0000000..6531856 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2(NO3)2 Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 4.3271e-05) +mat.add_nuclide('U234', 7.1442e-07) +mat.add_nuclide('U235', 1.7565e-08) +mat.add_nuclide('U238', 2.7748e-07) +mat.add_nuclide('N14', 1.1819e-04) +mat.add_nuclide('H1', 6.6271e-02) +mat.add_element('O', 3.3564e-02) +mat.add_nuclide('Th232', 1.9639e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-1/geometry.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/geometry.xml new file mode 100644 index 0000000..9740a83 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-1/materials.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/materials.xml new file mode 100644 index 0000000..e35486f --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-1/settings.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-1/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-2/generate_materials.py b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/generate_materials.py new file mode 100644 index 0000000..b444131 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2(NO3)2 Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 4.5093e-05) +mat.add_nuclide('U234', 7.4451e-07) +mat.add_nuclide('U235', 1.8305e-08) +mat.add_nuclide('U238', 2.8917e-07) +mat.add_nuclide('N14', 1.2248e-04) +mat.add_nuclide('H1', 6.6362e-02) +mat.add_element('O', 3.3628e-02) +mat.add_nuclide('B10', 2.6481e-07) +mat.add_nuclide('B11', 1.0659e-06) +mat.add_nuclide('Th232', 2.0489e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-2/geometry.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/geometry.xml new file mode 100644 index 0000000..5325611 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-2/materials.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/materials.xml new file mode 100644 index 0000000..c03d148 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-2/settings.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-2/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-3/generate_materials.py b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/generate_materials.py new file mode 100644 index 0000000..f8a64d9 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2(NO3)2 Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 4.6768e-05) +mat.add_nuclide('U234', 7.7216e-07) +mat.add_nuclide('U235', 1.8984e-08) +mat.add_nuclide('U238', 2.9991e-07) +mat.add_nuclide('N14', 1.2772e-04) +mat.add_nuclide('H1', 6.6413e-02) +mat.add_element('O', 3.3674e-02) +mat.add_nuclide('B10', 5.1591e-07) +mat.add_nuclide('B11', 2.0766e-06) +mat.add_nuclide('Th232', 2.1331e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-3/geometry.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/geometry.xml new file mode 100644 index 0000000..7cf326c --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-3/materials.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/materials.xml new file mode 100644 index 0000000..eefeab3 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-3/settings.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-3/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-4/generate_materials.py b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/generate_materials.py new file mode 100644 index 0000000..f2ae610 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2(NO3)2 Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 4.8433e-05) +mat.add_nuclide('U234', 7.9965e-07) +mat.add_nuclide('U235', 1.9660e-08) +mat.add_nuclide('U238', 3.1059e-07) +mat.add_nuclide('N14', 1.3173e-04) +mat.add_nuclide('H1', 6.6337e-02) +mat.add_element('O', 3.3653e-02) +mat.add_nuclide('B10', 7.6312e-07) +mat.add_nuclide('B11', 3.0716e-06) +mat.add_nuclide('Th232', 2.2133e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-4/geometry.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/geometry.xml new file mode 100644 index 0000000..d1c5209 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-4/materials.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/materials.xml new file mode 100644 index 0000000..55b25a9 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-4/settings.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-4/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-5/generate_materials.py b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/generate_materials.py new file mode 100644 index 0000000..6977d4c --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/generate_materials.py @@ -0,0 +1,31 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2(NO3)2 Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 5.0043e-05) +mat.add_nuclide('U234', 8.2623e-07) +mat.add_nuclide('U235', 2.0314e-08) +mat.add_nuclide('U238', 3.2091e-07) +mat.add_nuclide('N14', 1.3586e-04) +mat.add_nuclide('H1', 6.6329e-02) +mat.add_element('O', 3.3666e-02) +mat.add_nuclide('B10', 1.0114e-06) +mat.add_nuclide('B11', 4.0708e-06) +mat.add_nuclide('Th232', 2.2691e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-5/geometry.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/geometry.xml new file mode 100644 index 0000000..d769a82 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/geometry.xml @@ -0,0 +1,19 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-5/materials.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/materials.xml new file mode 100644 index 0000000..7063e28 --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/materials.xml @@ -0,0 +1,32 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-001/openmc/case-5/settings.xml b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-001/openmc/case-5/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file diff --git a/icsbep/openmc/u233-sol-therm-008/mcdc/u233-sol-therm-008.py b/icsbep/openmc/u233-sol-therm-008/mcdc/u233-sol-therm-008.py new file mode 100644 index 0000000..a8e807a --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-008/mcdc/u233-sol-therm-008.py @@ -0,0 +1,63 @@ +import mcdc +import numpy as np + + +############################## +#__________Materials__________ +############################## + +# Material Name: UO2(NO3)2 Solution +# S(a,b): c_H_in_H2O (Not Implemented) +# Depletable +m1 = mcdc.material(nuclides=[ + ['U233',3.3441e-05], + ['U235',1.0184e-08], + ['U238',2.5474e-07], + ['N14',7.4943e-05], + ['H1',0.066357], + ['O16',0.033456315249], + ['O17',1.2684751e-05], +# Material Name: Type 1100 Aluminum +m2 = mcdc.material(nuclides=[ + ['Al27',0.059881], + ['Si28',0.00020096847272000002], + ['Si29',1.0204605640000001e-05], + ['Si30',6.7269216400000005e-06], + ['Fe54',6.404951000000001e-06], + ['Fe56',0.0001005440332], + ['Fe57',2.3220002000000003e-06], + ['Fe58',3.090156e-07], + ['Cu63',3.5518206e-05], + ['Cu65',1.5845794e-05], + ['Mn55',1.4853e-05]]) +mvoid = mcdc.material(nuclides=[['N14',1e-10]]) +############################## +#__________Geometry__________ +############################## + +# Surface(s) +s1 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.011, bc='interface') +s2 = mcdc.surface('sphere', center=[0.0, 0.0, 0.0], radius=61.786, bc='vacuum') + +# Material Cell(s) +c1 = mcdc.cell(-s1, fill=m1) +c2 = mcdc.cell(+s1 & -s2, fill=m2) +# Root Universe Cells List: +u0_cells = [] +# Material Universe(s) + +############################## +#__________Settings__________ +############################## + +# Simulation Parameters +mcdc.eigenmode(N_inactive=20, N_active=180) +mcdc.setting(N_particle=10000) + +# Source Parameters +# Particle: neutron +# Space Type: box +mcdc.source(x=[-1.0,1.0], y=[-1.0,1.0], z=[-1.0,1.0], prob=1.0) + +mcdc.run() + diff --git a/icsbep/openmc/u233-sol-therm-008/openmc/generate_materials.py b/icsbep/openmc/u233-sol-therm-008/openmc/generate_materials.py new file mode 100644 index 0000000..a69868e --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-008/openmc/generate_materials.py @@ -0,0 +1,29 @@ +import openmc + +mats = openmc.Materials() + +mat = openmc.Material(1) +mat.name = "UO2(NO3)2 Solution" +mat.set_density('sum') +mat.add_nuclide('U233', 3.3441e-05) +mat.add_nuclide('U234', 5.2503e-07) +mat.add_nuclide('U235', 1.0184e-08) +mat.add_nuclide('U238', 2.5474e-07) +mat.add_nuclide('N14', 7.4943e-05) +mat.add_nuclide('H1', 6.6357e-02) +mat.add_element('O', 3.3469e-02) +mat.add_nuclide('Th232', 1.4756e-07) +mat.add_s_alpha_beta('c_H_in_H2O') +mats.append(mat) + +mat = openmc.Material(2) +mat.name = "Type 1100 Aluminum" +mat.set_density('sum') +mat.add_element('Al', 5.9881e-02) +mat.add_element('Si', 2.1790e-04) +mat.add_element('Fe', 1.0958e-04) +mat.add_element('Cu', 5.1364e-05) +mat.add_element('Mn', 1.4853e-05) +mats.append(mat) + +mats.export_to_xml() diff --git a/icsbep/openmc/u233-sol-therm-008/openmc/geometry.xml b/icsbep/openmc/u233-sol-therm-008/openmc/geometry.xml new file mode 100644 index 0000000..e2ad34b --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-008/openmc/geometry.xml @@ -0,0 +1,17 @@ + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-008/openmc/materials.xml b/icsbep/openmc/u233-sol-therm-008/openmc/materials.xml new file mode 100644 index 0000000..1e1b61d --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-008/openmc/materials.xml @@ -0,0 +1,30 @@ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + diff --git a/icsbep/openmc/u233-sol-therm-008/openmc/settings.xml b/icsbep/openmc/u233-sol-therm-008/openmc/settings.xml new file mode 100644 index 0000000..27048fc --- /dev/null +++ b/icsbep/openmc/u233-sol-therm-008/openmc/settings.xml @@ -0,0 +1,18 @@ + + + + + + eigenvalue + 200 + 20 + 10000 + + + + box + -1 -1 -1 1 1 1 + + + + \ No newline at end of file