浅谈铅基快堆的冷却剂

doi:10.11896/cldb.23020057

材料导报

2023, Vol. 37

Issue (S1): 23020057-8 https://doi.org/10.11896/cldb.23020057

金属与金属基复合材料

浅谈铅基快堆的冷却剂

冯琳娜¹, 严明宇^2,*, 恽迪^1,*

1 西安交通大学能源与动力工程学院,西安 712000
2 中国核动力研究设计院,成都 610041

Discussion on the Coolant of Lead-based Fast Reactors

FENG Linna¹, YAN Mingyu^2,*, YUN Di^1,*

1 School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an 712000, China
2 Nuclear Power Institute of China, Chengdu 610041, China

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摘要铅基快堆是第四代反应堆六种主要堆型之一。铅基快堆采用液态铅或液态铅铋合金作为冷却剂,具有显著的优势。冷却剂的物性显著地影响了反应堆物理、热工、安全、材料、结构、系统设备和运行维护等几乎所有关键属性,是反应堆技术体系的框架和主线。本文从熔点、固液转换特性、材料的腐蚀、²¹⁰Po的影响、放射性物质包容能力、冷却剂价格六个方面对铅和铅铋共晶合金这两种主要的铅基冷却剂进行探讨,分析了物性区别及其对反应堆的影响。铅铋快堆相较于铅冷快堆具有温度运行范围更宽、运维更灵活简便、系统更简单、安全性和经济性更好等优势,具有更广阔的应用前景。铅铋快堆是我国发展为核能综合利用大国强国的合理选择。

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	冯琳娜
	严明宇
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关键词: 铅基快堆冷却剂物性固有安全

Abstract: Lead-cooledfast reactor is one of the sixGIF definedgeneration IV reactor types. Use of liquid lead or liquid lead bismuth alloy as coolant in a lead-based fast reactor poses significant advantages. The physical properties of liquid lead strongly influence almost all key design elements of the reactor, including reactor physics, thermal-hydraulics, safety, materials, structure, system equipment, and operation maintenance, etc. In this paper, lead and lead bismuth eutectic alloys, the two main lead-based coolants, are discussed from six different aspects: melting point, solid-liquid conversion characteristics, corrosion of materials, impact of ²¹⁰Po, containing capacity of radioactive substances, and coolant cost effectiveness. The differences in physical properties and their impact on the reactors are analyzed. Compared to lead cooled fast reactors, lead bismuth fast reactors have advantages such as wider operation temperature range, more flexible and convenient operation and maintenance, simpler system, better safety and economy, and broader application prospects. Lead bismuth fast reactor is a reasonable choice for China whose current goal is to develop into a major power in the world arena of nuclear energy.

Key words: lead-based fast reactor coolant physical property intrinsic safety

发布日期: 2023-09-06

ZTFLH:

TL352.1

通讯作者: *严明宇,研究员级高级工程师,2007年毕业于东京工业大学原子炉专业,获博士学位,毕业后就职于中国核动力研究设计院,现主要从事反应堆工程设计。megatron-prime@hotmail.com;
恽迪,西安交通大学教授、博士生导师,陕西省青年拔尖人才计划入选者,陕西省青年百人学者,先后毕业于清华大学、伊利诺伊大学香槟分校,获博士学位。主要从事核燃料、材料、多尺度模拟、辐照效应等相关研究。发表论文40余篇。diyun1979@xjtu.edu.cn

作者简介: 冯琳娜,2008年6月于南京理工大学获得工学硕士学位。现为西安交通大学能源与动力工程学院博士研究生,在恽迪教授的指导下进行研究。目前主要研究领域为金属燃料性能分析。

引用本文:

冯琳娜, 严明宇, 恽迪. 浅谈铅基快堆的冷却剂[J]. 材料导报, 2023, 37(S1): 23020057-8.
FENG Linna, YAN Mingyu, YUN Di. Discussion on the Coolant of Lead-based Fast Reactors. Materials Reports, 2023, 37(S1): 23020057-8.

链接本文:

http://www.mater-rep.com/CN/10.11896/cldb.23020057 或 http://www.mater-rep.com/CN/Y2023/V37/IS1/23020057

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