Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code


Gunay M.

ACTA PHYSICA POLONICA A, cilt.128, 2015 (SCI İndekslerine Giren Dergi) identifier identifier

Özet

In this study, the effect of the radiation damage of spent fuel-grade plutonium content was investigated in the structural material of a designed fusion-fission hybrid reactor system. In this study, the molten salt-heavy metal mixtures 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, and 99-95% Li20Sn80-1-5% SFG-PuO2 were used as fluids. The fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In this study, damage to the total structural material and each 1.0 cm thickness thereof was measured as a function of radiation energy, using the selected fluid rates, 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.