Contributions of each isotope in structural material on radiation damage in a hybrid reactor

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% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% UO 2 , 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% NpO 2 , and 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% UCO were used as fluids. In this study, the effect on the radiation damage of spent fuel-grade (SFG)-PuO 2 , UO 2 , NpO 2 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.

Calculation of Fissile Fuel Production in Some Minor Actinides Based on Thorium

“…The reactor is shaped like a torus and shown in Figure 1. Li20Sn80 liquid layer; it is preferred because it significantly reduces the parameters that damage structural materials such as radiation and activation Abdou et al, 2005;Günay et al, 2011;Youssef and Abdou, 2000;Ying et al, 1999;Youssef et al, 2002;Günay, 2016). Beryllium was used as reflector.…”