Abstract
In this study, a hybrid reactor system was designed by using 99–95% Li20 Sn80 + 1-5% RG-Pu, 99–95% Li20 Sn80 + 1-5% RG-PuF4 , and 99–95% Li20 Sn80 + 1-5% RG-PuO2 fluids, ENDF/B-VII.0 evaluated nuclear data library and 9Cr2WVTa structural material. The fluids were used in the liquid first wall, liquid second wall (blanket) and shield zones of a fusion–fission hybrid reactor system. The neutron flux was calculated according to the mixture components, radial, energy spectrum in the designed hybrid reactor system for the selected fluids, library and structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code.
Highlights
The waste management required as a result of fuel burning to generate energy from traditional nuclear reactors is one of the most important problems today
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
The main objective of this study is to investigate the neutron flux according to the mixture components, radial, energy spectrum in the designed hybrid reactor system for the selected fluids, library and structural material
Summary
The waste management required as a result of fuel burning to generate energy from traditional nuclear reactors is one of the most important problems today. For this reason, hybrid reactor system has been developed where fusion and fission occur at the same time. The main objective of this study is to investigate the neutron flux according to the mixture components, radial, energy spectrum in the designed hybrid reactor system for the selected fluids, library and structural material
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