动态应变时效对核电材料环境致裂影响的研究现状与进展  

REVIEW ON RELATIONSHIP BETWEEN DYNAMIC STRAIN AGING AND ENVIRONMENTALLY ASSISTED CRACKING OF STRUCTURAL MATERIALS USED IN NUCLEAR POWER PLANTS

作　　者：谭季波[1] 吴欣强[1] 韩恩厚[1] 

机构地区：[1]中国科学院金属研究所金属腐蚀与防护国家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

出　　处：《中国腐蚀与防护学报》2012年第6期437-442,共6页Journal of Chinese Society For Corrosion and Protection

基　　金：国家科技重大专项(2010ZX06004-009);国家重点基础研究发展计划项目(2011CB610506);中国科学院金属研究所创新基金联合资助

摘　　要：综述了核级碳钢、低合金钢、不锈钢发生动态应变时效(DSA)的反常特征、影响因素及机制,讨论了DSA与高温高压水环境因素的交互作用对核电材料环境致裂的可能影响。指出了当前研究中存在的问题及进一步的研究方向。The paper summarized the anomalous deformation characteristics, influencing factors and mechanisms of dynamic strain aging （DSA） in nuclear-grade carbon steels, low alloy steels and austenitic stainless steels. The possible effects of the interaction between DSA and high temperature water on environmentally assisted cracking of structural materials used in nuclear power plants have been discussed. The coming possible research topics and directions are also proposed.

关 键 词：动态应变时效 核电材料 高温高压水 环境致裂 腐蚀疲劳 应力腐蚀 

分 类 号：TG172.8[金属学及工艺—金属表面处理]