While analysing the output files of SOURCES 4D, I noticed an incorrect value of the total neutron spectrum printed in outp2, for cases where spontaneous fission is the only contribution to neutron emission or in which the number of nuclides undergoing spontaneous fission is limited to one.
In particular, the values of the absolute total neutron spectrum are written under the normalized total neutron spectrum, while the absolute total neutron spectrum is zero.
I believe this issue was already present in SOURCES4C.
While analysing the output files of SOURCES 4D, I noticed an incorrect value of the total neutron spectrum printed in outp2, for cases where spontaneous fission is the only contribution to neutron emission or in which the number of nuclides undergoing spontaneous fission is limited to one.
In particular, the values of the absolute total neutron spectrum are written under the normalized total neutron spectrum, while the absolute total neutron spectrum is zero.
I believe this issue was already present in SOURCES4C.