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In this study, the effect of spent fuel grade plutonium content on  239–243 Pu 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 % Li 20 Sn 80 -1 – 5 % SFG-Pu, 99 – 95 % Li 20 Sn 80 -1 – 5 % SFG-PuF 4 , 99 – 95 % Li 20 Sn 80 -1 – 5 % SFG-PuO 2 . 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  238–242 Pu(n,γ) 239–243 Pu 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.

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