材料导报 2022, Vol. 36 Issue (Z1): 21010255-6
金属与金属基复合材料
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辐照后锆合金腐蚀与第二相非晶化研究概况
全琪炜1 , 刘向兵1 , 徐超亮1 , 张晏玮1 , 李远飞1 , 钱王洁1 , 贾文清1 , 吴奕初2 , 赵文增2
1 苏州热工研究院有限公司,江苏 苏州 215000 2 武汉大学物理科学与技术学院,武汉 430000
Summary of the Research on Zirconium Alloy Corrosion and Second Phase Amorphization After Irradiation
QUAN Qiwei1 , LIU Xiangbing1 , XU Chaoliang1 , ZHANG Yanwei1 , LI Yuanfei1 , QIAN Wangjie1 , JIA Wenqing1 , WU Yichu2 , ZHAO Wenzeng2
1 Suzhou Nuclear Power Research Institute Co., Ltd., Suzhou 215000, Jiangsu, China 2 School of Physics and Technology, Wuhan University, Wuhan 430000, China
摘要 锆合金因其优良性能在核电燃料包壳领域有着广泛应用,燃料包壳服役时的关注要点为其耐腐蚀性能,因实际堆内存在辐照因素影响材料组织和性能,辐照条件下锆合金的腐蚀机理逐渐成为当前研究热点。本文综述了国内外有关辐照对锆合金微观组织结构和耐腐蚀性能影响的研究进展,在此基础上探讨了辐照导致第二相非晶化的过程及其机理,主要包括Zr-Sn系和含Nb锆合金中第二相辐照非晶化行为的差异,由此分析不同类型第二相在辐照条件下加剧腐蚀效应的机理。最后基于分析讨论,提出锆合金在辐照条件下提升耐腐蚀性方面的设计思路,为深入研究辐照对锆合金腐蚀性能的影响提供参考,并对锆合金燃料包壳领域今后的研究方向作出展望。
关键词:
锆合金
氧化腐蚀
辐照
第二相
非晶化
Abstract: Zirconium alloy is widely used in fuel cladding due to excellent properties, and corrosion is one of the main concerns during its service term. Actually, the irradiation in reactor can affect the structure and performance of zirconium alloy, and therefore the research on the corrosion mechanism under irradiation gradually becomes one of the current hot spots. This paper reviews the domestic and foreign related research progress on the effects of irradiation on the microstructure and corrosion properties of zirconium alloys. It mainly includes the difference in the amorphization behavior of the second phase in the Zr-Sn series and the Nb-containing zirconium alloys, so as to analyze the mechanism of different types of second phases intensifying the corrosion effect under irradiation. Based on the analysis and discussion, the new idea for improving the corrosion resistance under irradiation is proposed, which provides reference to the effect of irradiation on corrosion properties of zirconium alloy, and prospects the future research direction of zirconium fuel cladding.
Key words:
zirconium alloy
oxidation corrosion
irradiation
second phase
amorphization
出版日期: 2022-06-05
发布日期: 2022-06-08
基金资助: 国家自然科学基金(11975171)
通讯作者:
liuxbing@cgnpc.com.cn
作者简介: 全琪炜,反应堆结构材料助理工程师。2017年6月本科毕业于东南大学材料科学与工程学院,2020年6月毕业于东南大学,获得工学硕士学位。2020年7月,加入中广核苏州热工研究院有限公司电站寿命管理技术中心,从事材料辐照效应研究工作,目前主要研究领域核材料的离子辐照效应。 刘向兵,中广核苏州热工研究院有限公司电站寿命管理技术中心副总工,正高级工程师。2010年1月毕业于北京科技大学,获材料学博士学位,2010—2012年在苏州热工研究院进行博士后研究工作,兼任江苏省仪器仪表学会无损检测仪器专业委员会会员、北京粉末冶金研究会副理事长、电力行业电力锅炉压力容器安全监督管理委员会专家等。主要从事核结构材料辐照效应研究,编著出版《核反应堆压力容器材料辐照脆化效应》专著1本,发表论文60余篇。
引用本文:
全琪炜, 刘向兵, 徐超亮, 张晏玮, 李远飞, 钱王洁, 贾文清, 吴奕初, 赵文增. 辐照后锆合金腐蚀与第二相非晶化研究概况[J]. 材料导报, 2022, 36(Z1): 21010255-6.
QUAN Qiwei, LIU Xiangbing, XU Chaoliang, ZHANG Yanwei, LI Yuanfei, QIAN Wangjie, JIA Wenqing, WU Yichu, ZHAO Wenzeng. Summary of the Research on Zirconium Alloy Corrosion and Second Phase Amorphization After Irradiation. Materials Reports, 2022, 36(Z1): 21010255-6.
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http://www.mater-rep.com/CN/
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http://www.mater-rep.com/CN/Y2022/V36/IZ1/21010255
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