Contributions of each isotope in some fluids on neutronic performance in a fusion–fission hybrid reactor: a Monte Carlo method

Abstract

In the present investigation, a fusion–fission hybrid reactor system was designed by using 9Cr2WVTa ferritic steel structural material and 99–95 % Li20Sn80-1–5 % SFG-Pu, 99–95 % Li20Sn80-1–5 % SFG-PuF4, 99–95 % Li20Sn80-1–5 % SFG-PuO2 the molten salt-heavy metal mixtures, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion–fission hybrid reactor system. Beryllium zone with the width of 3 cm was used for the neutron multiplicity between liquid first wall and blanket. The contributions of each isotope in fluids on the nuclear parameters of a fusion–fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, heat deposition rate were computed in liquid first wall, blanket and shield zones. Three-dimensional analyses were performed by using Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.