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中国腐蚀与防护学报  2022, Vol. 42 Issue (1): 9-15    DOI: 10.11902/1005.4537.2021.094
  综合评述 本期目录 | 过刊浏览 |
核电结构材料腐蚀疲劳裂纹扩展行为研究现状与进展
张兹瑜, 吴欣强(), 韩恩厚, 柯伟
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
A Review on Corrosion Fatigue Crack Growth Behavior of Structural Materials in Nuclear Power Plants
ZHANG Ziyu, WU Xinqiang(), HAN En-Hou, KE Wei
CAS 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
全文: PDF(591 KB)   HTML
摘要: 

综述了核电结构材料腐蚀疲劳裂纹扩展的研究现状及环境、力学、材料等因素的影响规律，讨论了高温高压水环境中考虑环境效应的疲劳裂纹扩展模型，提出了当前核电结构材料高温高压水腐蚀疲劳裂纹扩展机制及模型研究面临的主要问题及未来可能的研究方向。
关键词 ： 核电结构材料,  高温高压水,  腐蚀疲劳,  裂纹扩展机理,  裂纹扩展模型    
Abstract：

Structural materials in nuclear power plants are subjected to corrosion fatigue (CF) during long-term service in high temperature pressurized water. The mechanism and data base of CF crack growth are essential to the design, operation and life management of nuclear power plants. This paper reviewed the present research status on CF crack growth behavior. The effect of environmental, mechanical and material’s factors were introduced, while the fatigue crack growth model was discussed by taking the environment effect in high temperature pressurized water into consideration. Challenges and trends for research of fatigue crack growth mechanism and model for structural materials in nuclear power plants were also briefly addressed.
Key words： structural materials in nuclear power plant    high temperature pressurized water    corrosion fatigue    crack growth mechanism    crack growth model
收稿日期: 2021-04-29     
ZTFLH:  TG172  
基金资助:中核集团青年英才项目及国家科技重大专项(2017ZX 06002003-004-002)
通讯作者: 吴欣强     E-mail: xqwu@imr.ac.cn
Corresponding author: WU Xinqiang     E-mail: xqwu@imr.ac.cn
作者简介: 张兹瑜，男，1991年生，博士，助理研究员
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张兹瑜
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引用本文:

张兹瑜, 吴欣强, 韩恩厚, 柯伟. 核电结构材料腐蚀疲劳裂纹扩展行为研究现状与进展[J]. 中国腐蚀与防护学报, 2022, 42(1): 9-15.
Ziyu ZHANG, Xinqiang WU, En-Hou HAN, Wei KE. A Review on Corrosion Fatigue Crack Growth Behavior of Structural Materials in Nuclear Power Plants. Journal of Chinese Society for Corrosion and protection, 2022, 42(1): 9-15.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2021.094      或      https://www.jcscp.org/CN/Y2022/V42/I1/9

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