Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model
NUCLEAR ENERGY SCIENCE AND ENGINEERING|更新时间:2024-10-25
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Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model
封面论文
“In the field of nuclear energy, researchers have achieved the ability of the molten salt reactor 233U to self sustain and incinerate reactor grade plutonium by adding reactor grade plutonium online based on FLiBe carrier salt. Research has found that 233U self-sustaining can be achieved within a large range of molten salt volume ratio of 10% to 85%, with the best proliferation effect observed at approximately 43% molten salt volume ratio. At the same time, the dependence on plutonium is the highest when 43% of the molten salt is used, and the dependence on plutonium is relatively small when the volume of molten salt is small or large; When the volume of molten salt is relatively small, it is more conducive to the utilization of plutonium, and the incineration rate of plutonium is the highest when the volume ratio of molten salt is 10%~15%, about 75%. In addition, the neutron loss rate is approximately proportional to the dependence on plutonium, and has a relatively small impact on the self-sustaining performance of 233U.”
YU Changqing,ZHU Guifeng,XIA Shaopeng,et al.Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model[J].NUCLEAR TECHNIQUES,2020,43(03):51-58.
YU Changqing,ZHU Guifeng,XIA Shaopeng,et al.Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model[J].NUCLEAR TECHNIQUES,2020,43(03):51-58. DOI: 10.11889/j.0253-3219.2020.hjs.43.030601.
Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model封面论文