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轻水堆核电站乏燃料贮存格架及运输容器用硼铝材料介绍 被引量:4

Introduction to Boron-Aluminum Material for Spent-fuel Storage Racks and Transport Cask in LWR Nuclear Power Plants
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摘要 介绍了轻水堆核电站乏燃料贮存格架及运输容器用硼铝中子吸收材料的研究、开发和使用现状,主要包括铝/硼合金、铝/碳化硼合金、铝/碳化硼金属陶瓷和铝/碳化硼金属基复合材料,最后对这些已开发的硼铝中子吸收材料从材料性能、使用经验和经济学等方面做了综合的对比和分析,认为目前第三代核电站普遍使用的铝/碳化硼金属基复合材料虽然从理论和试验上认为可满足要求,但还需经过长期的实际使用验证,而我国也应当开发能够满足我国核能行业快速发展需求且具有自我知识产权的中子吸收材料。 The research, development and application actualities of boron-aluminum neutron absorber material for spent nuclear fuel storage and transportation application in light water nuclear power plants are introduced, inclu ding Al/B alloy, Al/B4C alloy, Al/B4C eermets, and Al/B4C metal matrix composites. Finally, a general comparation between all sorts of boron-aluminum neutron absorber materials is given. It is concluded that although Al/B4 C metal matrix composites which is widely used in the 3rd generation PWR all around the world have been qualified through theory analysis and experiment test, they still need to be proved in the long term operation. China should also develop the neutron absorber material which could satisfy the need of rapidly growing nuclear power industry.
出处 《材料导报(纳米与新材料专辑)》 EI CAS 2014年第2期466-470,486,共6页
关键词 硼铝材料 中子吸收材料 核电站 boron-aluminum material, neutron absorber material, nuclear power plants
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参考文献9

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