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

İnönü University, Science and Art Faculty, Physics Department, Malatya, Turkey

Published online: 15 November 2016

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% Li₂₀Sn₈₀ + 5% SFG-PuO₂ and 2-10% UO₂, 93–85% Li₂₀Sn₈₀ + 5% SFG-PuO₂ and 2-10% NpO₂, and 93–85% Li₂₀Sn₈₀ + 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.