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熔盐堆临界与7Li丰度变化的核安全分析

Nuclear Safety Analysis of Molten Salt Reactor Criticality with Changes in 7Li Abundance

中文摘要英文摘要

熔盐堆是六种第四代反应堆之一,其使用液态核燃料,与常规固态核燃料堆型不一样。为做好堆芯设计管理和核安全监管,有必要对其7Li丰度与核临界参数的关系进行分析。本研究通过参考具有工程实践的熔盐堆进行建模,运用软件仿真模拟计算,分析不同7Li丰度燃料盐对熔盐堆反应性的影响,分析核临界参数变化的规律。通过迭代计算,快速精确找到熔盐堆核临界时的7Li丰度值。最终得出结论,熔盐堆反应性随着燃料盐7Li丰度的增加而增加,且在熔盐堆反应性变化率也与7Li丰度有关。根据本研究分析成果进行深入探讨,从法律法规角度总结相关管理要求,从审管角度提出应该关注的建议要点。

Background]: Molten salt reactor is one of the six internationally recognized and recommended fourth generation reactors , which is different from conventional solid-state nuclear fuel reactors. It is necessary to analyze the relationship between 7Li abundance and nuclear critical parameters in order to do a good job in core design management and nuclear safety supervision. [Purpose]: This study modeled a molten salt reactor with reference to engineering practice, and used software simulation calculations to analyze the impact of different 7Li abundance fuel salts on the reactivity of the molten salt reactor, and to analyze the changes in nuclear critical parameters. [Methods]: By iterative calculation, quickly and accurately find the 7Li abundance value at the critical state of the molten salt reactor core. [Results]: The final conclusion is that the reactivity of the molten salt reactor increases with the increase of fuel salt 7Li abundance, and the rate of change in reactivity of the molten salt reactor is also related to 7Li abundance. [Conclusions]: Based on the analysis results of this study, conduct in-depth exploration, summarize relevant management requirements from the perspective of laws and regulations, and propose key points for attention from the perspective of review and management.

姚永奎、杨震、戴志敏、邹杨

10.12074/202408.00126

核反应堆工程核燃料、核燃料生产

熔盐堆燃料盐7Li丰度核临界核安全

Molten salt reactorFuel saltbundance of 7LiNuclear criticalityNuclear safety

姚永奎,杨震,戴志敏,邹杨.熔盐堆临界与7Li丰度变化的核安全分析[EB/OL].(2024-08-15)[2025-08-11].https://chinaxiv.org/abs/202408.00126.点此复制

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