Comparative Study on the Reduction of Tritium Breeding Ratio Caused by Inventory Changes of a Solid-State Tritium Breeding Blanket in a Fusion Demonstration Reactor Using MCNP and FISPACT-II

IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Journal of Fusion Energy Pub Date : 2024-08-08 DOI:10.1007/s10894-024-00455-2
Byung Chul Kim
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Abstract

The self-sufficient supply of tritium in the deuterium-tritium nuclear fusion demonstration reactor (DEMO) is a fundamental design requirement. But, it is hindered by depletion of tritium breeding materials resulting in reduction of tritium breeding ratio (TBR) less than the initial design value especially in the solid-state tritium breeding blanket (TBB) of the DEMO. Unlike the liquid tritium breeding blanket of DEMO, compensation measures of the depleted breeding material in the solid-state TBB will be its substitution depending on the reduction rate of TBR. To estimate the replacement period of the solid-state TBB, it is required to estimate the reduction rate of TBR according to the operation conditions of the DEMO and the physical configuration of a solid-state TBB. In this study, the representative simulation codes, MCNP and FISPACT-II, are used for assessment of the reduction rate of TBR with the benchmarking model which is modified from the one poloidal segment of the TBB in the Korean-DEMO. After 3 full power-year operations with the neutron irradiation with the benchmarking model, the TBR simulated by MCNP is reduced to 96.84% of the initially calculated TBR, but the TBR calculated by FISPACT-II is reduced to 90.57% of the initially calculated TBR.

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利用 MCNP 和 FISPACT-II 对聚变示范反应堆中固态氚孕育毯库存变化导致的氚孕育率降低进行比较研究
氘氚核聚变示范反应堆(DEMO)中氚的自给自足是一项基本设计要求。但是,由于氚孕育材料的耗竭,导致氚孕育率(TBR)低于初始设计值,特别是在 DEMO 的固态氚孕育毯(TBB)中,氚孕育率的降低阻碍了氚的自给自足。与 DEMO 的液态氚孕育毯不同,固态氚孕育毯中贫化孕育材料的补偿措施是根据氚孕育率的降低率进行替代。为了估算固态 TBB 的替换周期,需要根据 DEMO 的运行条件和固态 TBB 的物理结构估算 TBR 的减少率。本研究使用 MCNP 和 FISPACT-II 这两个具有代表性的仿真代码来评估 TBR 的减少率。在基准模型的中子辐照下,经过 3 个全功率年运行后,MCNP 模拟的 TBR 降至最初计算 TBR 的 96.84%,而 FISPACT-II 计算的 TBR 降至最初计算 TBR 的 90.57%。
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来源期刊
Journal of Fusion Energy
Journal of Fusion Energy 工程技术-核科学技术
CiteScore
2.20
自引率
0.00%
发文量
24
审稿时长
2.3 months
期刊介绍: The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews. This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.
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