Dear FLUKA experts,
I want to simulate the magnitude and distribution of neutron fluxes produced in the reactor core by several different external neutron sources.
The reactor uses UN as the fuel and BeO as the reflector layer.
The external neutron sources include: 1). spontaneous fission neutron sources, californium-252 (Cf-252).
2). antimony(Sb-124)-beryllium source: Sb-124 is a source of strong gamma rays emitter, while Be-9 is a neutron emitter element.
For 1), I tried BEAM card with an ISOTOPE particle, the HI-PROPE card defining Cf-252 (even the mass number in HI-PROPE card is limited to 247.) and the RADDECAY card to define the semi-analoge mode. However, the results from the USRBIN and USRTRACK card is still zero. For 2), the same zero results are produced.
So, I don’t know how to use FLUKA to simulate this process. Thanks in advance for further explanation.