The production of 238–242Pu(n,γ)239–243Pu fissionable fluids in a fusion-fission hybrid reactor

Abstract

Abstract In this study, the effect of spent fuel grade plutonium content on 239–243Pu was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99 – 95 % Li20Sn80-1 – 5 % SFG-Pu, 99 – 95 % Li20Sn80-1 – 5 % SFG-PuF4, 99 – 95 % Li20Sn80-1 – 5 % SFG-PuO2. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of 238–242Pu(n,γ)239–243Pu was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0.