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Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water |
JIAO Yang, ZHANG Shenghan( ), TAN Yu |
Department of Environment Science and Engineering, North China Electric Power University, Baoding 071003, China |
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Abstract Stress corrosion cracking behavior (SCC) of typical nuclear structural materials stainless steel in high-temperature and high-pressure water was reviewed. The effect of material type, mechanical properties, water chemistry on the sensitivity, initiation and propagation of cracks were discussed. The development of the zinc injection technology in the coolant system and its inhibitory effect on the primary side stress corrosion (PWSCC) were introduced. Finally, by taking various factors and actual operating conditions into consideration, the method of reducing the sensitivity of SCC was summarized, and the problems that should be focused on in future research were proposed.
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Received: 12 June 2020
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Corresponding Authors:
ZHANG Shenghan
E-mail: shenghan_zhang@126.com
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About author: ZHANG Shenghan, E-mail: shenghan_zhang@126.com
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