耐事故燃料包壳用FeCrAl不锈钢的研究进展  

Research Progress in the FeCrAl Alloys for Accident Tolerant Fuel Cladding

作　　者：周军[1] 邱绍宇[1] 杜沛南 孙永铎[1] 王辉[1] ZHOU Jun;QIU Shaoyu;DU Peinan;SUN Yongduo;WANG Hui(National Key Laboratory of Nuclear Fuel and Materials,Nuclear Power Institute of China,Chengdu 610041)

机构地区：[1]中国核动力研究设计院反应堆燃料及材料重点实验室,成都610041

出　　处：《材料导报》2017年第A02期47-51,共5页Materials Reports

摘　　要：3.11日本福岛核事故后,国内外围绕提高核燃料元件的事故包容能力和固有安全性课题开展了大量的耐事故燃料(ATF)的研发工作,其中性能更先进的包壳材料是ATF研究的前沿和难点。Fe Cr Al合金优良的高温性能结合管材制备工艺的技术成熟度和经济性,促使该合金包壳成为近期ATF包壳研发的首选目标。简介了国外在ATF包壳候选材料的筛选和Fe Cr Al不锈钢上的研究进展,综述了ATF包壳用Fe Cr Al不锈钢高温蒸汽氧化性能、力学性能、中子辐照性能和应力腐蚀性能等方面的研究现状,指出了Fe Cr Al包壳研制和工程应用等方面需突破的关键技术和研究方向,其中成分优化控制及制备工艺、中子辐照性能和应力腐蚀性能等工程应用的评价是未来研究的重点和难点。Since the nuclear accident in Japan on March 11th in 2011,considerable research on accident tolerant fuel(ATF)have been developed to provide larger safety margins,and research and development on advanced materials for cladding is an important component.Besides of excellent steam oxidation resistance of FeCrAl alloys,outstanding technological maturity and economy of processing technique of tube made the FeCrAl claddings become recent target for ATF claddings.The choice of candidate cladding materials and development of FeCrAl is presented in this paper.The application properties of FeCrAl,such asresistance on high temperature steam oxidation resistance,mechanical properties,resistance on neutron irradiation and SCC(stress corrosion crack)are also summarized.Base on the investigation,the key issue of research and application of FeCrAl cladding material are discussed.It is indicated that the optimization of alloy composition,process technology and evaluation of resistance on neutron irradiation and SCC of FeCrAl should be focused in father research.

关 键 词：耐事故燃料 FECRAL 高温蒸汽氧化性能 力学性能 中子辐照性能 应力腐蚀裂纹 

分 类 号：TL341[核科学技术—核技术及应用]