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用于核电推进的30 kWe反应堆电源堆芯设计 被引量:5

Core Design of 30 kWe Reactor Power System for Use on NEP
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摘要 核电推进(NEP)堆芯采用液态金属冷却,根据冷却方式的不同,设计了回路堆和热管堆两种堆型备选,并采用蒙特卡罗方法的MCNP程序对其有效增殖因子、功率分布等堆芯物理参数进行了计算,最后从两种堆型固有特点出发分析其优缺点。提出了临界安全设计的两种优化方向,列出了反应堆可能面临的特殊临界安全问题并做了理论分析和计算,最终通过合理布置谱移吸收体(SSA)材料的位置解决了特殊临界安全问题。计算结果表明两种堆芯设计满足物理和热工设计要求。 Nuclear electric propulsion(NEP)reactor core is cooled by liquid metal. Depending on the cooling mode loop reactor and heat pipe reactor were designed. The effective multiplication factor and power distribution were calculated with MCNP code,and then the advantages and disadvantages were analyzed based on their inherent characteristics. Optimization directions about the two critical safety design were proposed. The potential special criticality safety issues were listed,and a theoretical analysis and calculation were carried out. The special criticality safety issues was solved by a reasonable arrangement of spectral shift absorber material. The calculate results show that two kinds of reactor design meet the physical and thermal-hydraulic design requirements.
作者 高剑 郭键 赵守智 GAO Jian;GUO Jian;ZHAO Shou-zhi(China Institute of Atomic Energy,Beijing 102413,Chin)
出处 《核科学与工程》 CAS CSCD 北大核心 2018年第3期347-352,共6页 Nuclear Science and Engineering
关键词 回路堆 热管堆 堆芯物理参数 临界安全 谱移吸收体 Loop reactor Heat pipe reactor Core physical parameters Criticality safety Spectral shift absorber
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  • 2Stanley K. Borowski, Robert R. Corban, Melissa L. McGuire, et al. Nuclear thermal rocket/Vehicle design options for future NASA missions to the Moon and Mars [R]. NASA technical memorandum 107071, AIAA 93-4170.
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