中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials

文献类型:期刊论文

作者Han En-Hou1,2,3; Wang Jianqiu2
刊名ACTA METALLURGICA SINICA
出版日期2023-04-11
卷号59期号:4页码:513-522
关键词surface state corrosion stress corrosion irradiation-assisted stress corrosion nuclear material stainless steel nickel-based alloy
ISSN号0412-1961
DOI10.11900/0412.1961.2023.00123
通讯作者Han En-Hou(ehhan@scut.edu.cn)
英文摘要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.
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
语种英语
WOS记录号WOS:000980757300008
出版者SCIENCE PRESS
资助机构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
源URL[http://ir.imr.ac.cn/handle/321006/177861]  
专题金属研究所_中国科学院金属研究所
通讯作者Han En-Hou
作者单位1.Inst Corros Sci & Technol, Guangzhou 510535, Peoples R China
2.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, 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.

入库方式: OAI收割

来源:金属研究所

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