核用结构材料在高温高压水中应力腐蚀裂纹萌生研究进展  

Review of Stress Corrosion Crack Initiation of Nuclear Structural Materials in High Temperature and High Pressure Water

作　　者：刘保平 张志明[1,3] 王俭秋 韩恩厚[1] 柯伟[1] LIU Baoping;ZHANG Zhiming;WANG Jianqiu;HAN En-Hou;KE Wei(Key Laboratory of Nuclear Materials and Safety Assessment,Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials,Institute of Metal Research,Chinese Academy of Sciences,Shenyang 110016,China;School of Materials Science and Engineering,University of Science and Technology of China,Shenyang 110016,China;Institute of Corrosion Science and Technology,Guangzhou 510700,China)

机构地区：[1]中国科学院金属研究所中国科学院核用材料与安全评价重点实验室,辽宁省核电材料安全与评价技术重点实验室,沈阳110016 [2]中国科学技术大学材料科学与工程学院,沈阳110016 [3]广东腐蚀科学与技术创新研究院,广州510700

出　　处：《中国腐蚀与防护学报》2022年第4期513-522,共10页Journal of Chinese Society For Corrosion and Protection

基　　金：国家重点研发计划(2017YFB0702100)。

摘　　要：对核电站常用不锈钢和镍基合金等结构材料在服役的高温高压水中的应力腐蚀裂纹萌生测试的实验方法、评价指标、影响因素和萌生机理等几个方面进行论述,并指出目前研究的不足和未来研究趋势。In this paper, the test methods, evaluation indexes, influencing factors and initiation mechanism related with the stress corrosion cracking in high temperature and high pressure water for structural materials such as stainless steels and nickel-based alloys commonly used in nuclear power plants are reviewed, and the shortcomings of current research and the future research trends are also pointed out.

关 键 词：核电站 结构材料 高温高压水 应力腐蚀开裂 萌生机理 

分 类 号：TG174[金属学及工艺—金属表面处理]