Abstract
In this study, the fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. In this study, salt-heavy metal mixtures consisting of 93–85% Li20 Sn80 + 5% SFG-PuO2 and 2-10% UO2 , 93–85% Li20 Sn80 + 5% SFG-PuO2 and 2-10% NpO2 , and 93–85% Li20 Sn80 + 5% SFG-PuO2 and 2-10% UCO were used as fluids. In this study, the effect on the radiation damage of spent fuel-grade (SFG)-PuO2 , UO2 , NpO2 and UCO contents was investigated in the structural material of a designed fusion–fission hybrid reactor system. In the designed hybrid reactor system were investigated the effect on the radiation damage of the selected fluid according to each isotopes of structural material in the structural material for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.
Highlights
Hybrid reactor system has been developed where fusion and fission occur at the same time
A substantial amount of spent fuel grade (SFG) plutonium (Pu) from current nuclear reactors has been stored for future use
9Cr2WVTa ferritic steel was chosen as a structural material because it has low activation, which can help to extend the lifetime of the reactor system
Summary
Hybrid reactor system has been developed where fusion and fission occur at the same time.
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