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面向不同先进反应堆应用的新型不锈钢包壳研发进展 被引量:7

Progress in Research and Development of StainlessSteel Fuel Cladding for Variant Advanced Nuclear Reactors
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摘要 作为核反应堆的关键部件材料之一,核燃料的包壳服役性能严重制约核反应安全、性能和用途设计。新型不锈钢已成为未来先进反应堆核燃料用包壳的主要候选材料之一。本文概述国外不锈钢包壳材料研发进展,着重介绍我国在Fe Cr Al等新型包壳材料研制等方面取得的成果。面向未来不同需求的先进反应堆,这些自主研发的新型不锈钢包壳材料将为我国实现由核电大国向核电强国的转变提供有力支撑。 Currently, the global nuclear power is vigorously improving the inherent safety of the Generation Ⅲ nuclear power technology, promoting transformation of the Generation IV nuclear power technology from theoreticstudy to practical application, and actively developing multi-purpose small reactors. The improvement of these nuclear power technologies is inseparable from the development of nuclear materials. The fuel cladding, as one of the core and critical components of the nuclear reactor, seriously restricts the safety, performance and application design of a nuclear reactor. The new stainless steels have become one of the main candidate fuel cladding materials for future advanced reactors. In this paper, the foreign research progress of stainless steels for fuel claddings is summarized, and the domestic achievements in the research and development of new fuel cladding materials such as FeCrAl are emphatically introduced. These new self-developed stainless steels oriented to the future advanced reactors will provide strong support for China’s transformation from a great nuclear power country to a powerful one in the world.
作者 陈平 张瑞谦 段振刚 高士鑫 杜沛南 邱玺 周毅 尹春雨 何琨 何梁 CHEN Ping;ZHANG Ruiqian;DUAN Zhengang;GAO Shixin;DU Peinan;QIU Xi;ZHOU Yi;YIN Chunyu;HE Kun;HE Liang(Key Laboratory of Nuclear Reactor System Design Technology of Nuclear Power Institute of China,Chengdu 610213;Key Laboratory for Reactor Fuel and Materials of Nuclear Power Institute of China,Chengdu 610213)
出处 《中国基础科学》 2021年第4期1-8,共8页 China Basic Science
基金 国家重点研发计划项目(2019YFB1901000) 核技术联合基金重点支持项目(U1867201)。
关键词 核反应堆 不锈钢 燃料包壳 耐事故燃料 nuclear reactor stainless steel fuel cladding accident tolerant fuel
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