Abstract
In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 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 , as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion–fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR ), energy multiplication factor (M ), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Three-dimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.
Highlights
The fuels used in hybrid reactor systems are generally deuterium–tritium (D-T) or deuterium–deuterium (D-D) fuels
The plasma is surrounded by a wall made of fertile material, which cannot undergo the fusion reaction with thermal neutrons, but can undergo conversion with high energy neutrons, such as the 14.1 MeV neutrons produced by the fusion reaction
The fluids used in order to decrease amount of reactor grade Pu were used in the liquid first wall, blanket and shield zones of hybrid reactor system
Summary
The fuels used in hybrid reactor systems are generally deuterium–tritium (D-T) or deuterium–deuterium (D-D) fuels. The hybrid reactor produces 30 times more nuclear fuel per nuclear energy quantity than fast reactors [1,2,3,4,5,6]. The hybrid reactor system can generate secure energy in large quantities with D-T fuel usage and subcritical study. It enables the production of a selfsufficient fuel for the reactor through the reaction of the neutrons released by the plasma. The reactor-grade Pu in present nuclear power stations as fuel can use to reduce the trans-uranium content of spent nuclear fuel. In this study, radioactive materials with a plutonium additive were used in the hybrid reactor system to reduce the amount of reactor grade Pu used The reactor-grade Pu in present nuclear power stations as fuel can use to reduce the trans-uranium content of spent nuclear fuel. in this study, radioactive materials with a plutonium additive were used in the hybrid reactor system to reduce the amount of reactor grade Pu used
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