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Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials
Han En-Hou1,2,3; Wang Jianqiu1
通讯作者Han En-Hou(ehhan@scut.edu.cn)
2023-04-11
发表期刊ACTA METALLURGICA SINICA
ISSN0412-1961
卷号59期号:4页码:513-522
摘要Global nuclear power events are often caused by local corrosion, which starts at the surface. The effect of the surface state on corrosion and the interaction among corrosion, irradiation, and stress are important technical problems affecting the safety, reliability, and economy of nuclear power plants. In this paper, supported by a series of national projects in the last 10 years, the various surface state effects, for key structural materials used in nuclear power plants after surface finishing, grinding, machining, or scratching, on corrosion and stress corrosion behaviors in the simulated primary water of nuclear power plants are reviewed. The results show that surface grinding, scratching, or cutting can cause the formation of microstructures of different gradients near the surface and also cause large differences in surface deformation. For example, the residual compressive stress is greater than the yield stress in the superficial surface of the scratch; the different cutting parameters can cause the various gradient structures of the nanocrystalline and grain distortion zones to form along the depth of the cutting surface with similar surface roughness. Such microstructures and local stress-strain conditions lead to significant differences in corrosion resistance. For example, the number of stress corrosion cracks is positively correlated with scratch depth. Under the combined action of irradiation, corrosion, and stress, irradiation-assisted stress corrosion is further enhanced. Finally, the future research trend on the topic is forecast.
关键词surface state corrosion stress corrosion irradiation-assisted stress corrosion nuclear material stainless steel nickel-based alloy
资助者National Basic Research Program of China ; National Science and Technology Major Project of China ; National Key Research and Development Program of China ; Key Programs of Chinese Academy of Sciences ; Key Research Program of Frontier Sciences, Chinese Academy of Sciences
DOI10.11900/0412.1961.2023.00123
收录类别SCI
语种英语
资助项目National Basic Research Program of China[2011CB610500] ; National Basic Research Program of China[2006CB610500] ; National Science and Technology Major Project of China[2011ZX06004-009] ; National Key Research and Development Program of China[2016YFE0105200] ; Key Programs of Chinese Academy of Sciences[ZDRW-CN-2017-1] ; Key Research Program of Frontier Sciences, Chinese Academy of Sciences[QYZDY-SSW-JSC012]
WOS研究方向Metallurgy & Metallurgical Engineering
WOS类目Metallurgy & Metallurgical Engineering
WOS记录号WOS:000980757300008
出版者SCIENCE PRESS
引用统计
被引频次:3[WOS]   [WOS记录]     [WOS相关记录]
文献类型期刊论文
条目标识符http://ir.imr.ac.cn/handle/321006/177862
专题中国科学院金属研究所
通讯作者Han En-Hou
作者单位1.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
2.Inst Corros Sci & Technol, Guangzhou 510535, Peoples R China
3.South China Univ Technol, Sch Mat Sci & Engn, Guangzhou 511442, Peoples R China
推荐引用方式
GB/T 7714
Han En-Hou,Wang Jianqiu. Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials[J]. ACTA METALLURGICA SINICA,2023,59(4):513-522.
APA Han En-Hou,&Wang Jianqiu.(2023).Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials.ACTA METALLURGICA SINICA,59(4),513-522.
MLA Han En-Hou,et al."Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials".ACTA METALLURGICA SINICA 59.4(2023):513-522.
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