核电站用不锈钢在高温高压水中应力腐蚀开裂行为的研究进展

Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water

综述了作为核电结构材料的不锈钢在高温高压水环境中的应力腐蚀开裂(SCC)行为,讨论了材料性能、加载方式、水化学环境等因素对应力腐蚀敏感性、裂纹萌生与扩展速率的影响,介绍了较成熟锌注入技术的发展历程及其对压水堆一次侧应力腐蚀(PWSCC)的影响作用。最后综合考虑各方面因素和实际运行情况,总结了降低SCC敏感性的方法,并提出未来研究中应重点关注的问题。

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.