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| 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 |
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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.
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Received: 19 August 2013
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