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中国腐蚀与防护学报  2014, Vol. 34 Issue (1): 37-45    DOI: 10.11902/1005.4537.2013.175
  综述 本期目录 | 过刊浏览 |
核电结构材料应力腐蚀开裂的研究现状与进展
马 成 彭群家 韩恩厚 柯 伟
中国科学院金属研究所 金属腐蚀与防护国家重点实验室 沈阳 110016
Review of Stress Corrosion Cracking of Structural Materials in Nuclear Power Plants
MA Cheng, PENG Qunjia, HAN En-Hou, KE Wei
State Key Laboratory of Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
全文: PDF(1404 KB)   HTML
摘要: 围绕应力腐蚀行为的实验研究方法、影响因素以及应力腐蚀机制的理论分析等几个方面综述了核电结构材料应力腐蚀研究的现状,讨论了研究中亟待解决的问题,指出了研究的发展方向与趋势。
关键词 核电结构材料高温高压水应力腐蚀冷加工焊接件    
Abstract:The structural materials used in light water reactors (LWR) such as nickel based alloys and stainless steels have been found to be susceptible to stress corrosion cracking (SCC) in high temperature water. In this review, we summarized the research progress and current status on SCC of the structural materials used in LWR in terms of experimental methods, factors influencing SCC and the mechanisms of SCC. The research hotspots like the influence of cold-working and the SCC of weld joints were discussed. Some of the challenges and perspectives for the research of SCC in the future were also briefly addressed.
Key wordsstructural materials of light water reactor    high temperature water    stress corrosion cracking    cold working    weld joint
收稿日期: 2013-08-19     
ZTFLH:  TG174  
基金资助:中国科学院“百人计划”项目资助
通讯作者: 彭群家,E-mail:qunjiapeng@imr.ac.cn   
作者简介: 马成,男,1988年生,硕士生,研究方向为核电结构材料的应力腐蚀

引用本文:

马成, 彭群家, 韩恩厚, 柯伟. 核电结构材料应力腐蚀开裂的研究现状与进展[J]. 中国腐蚀与防护学报, 2014, 34(1): 37-45.
MA Cheng, PENG Qunjia, HAN En-Hou, KE Wei. Review of Stress Corrosion Cracking of Structural Materials in Nuclear Power Plants. Journal of Chinese Society for Corrosion and protection, 2014, 34(1): 37-45.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2013.175      或      https://www.jcscp.org/CN/Y2014/V34/I1/37

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