| 徐海波,徐祺,邱绍宇.法国核电应力腐蚀问题对我国核电技术发展的启示[J].装备环境工程,2024,2021(4):135-139. XU Haibo,XU Qi,QIU Shaoyu.Inspiration of Stress Corrosion in French Nuclear Power on Development of Nuclear Power Technology in China[J].Equipment Environmental Engineering,2024,2021(4):135-139. |
| 法国核电应力腐蚀问题对我国核电技术发展的启示 |
| Inspiration of Stress Corrosion in French Nuclear Power on Development of Nuclear Power Technology in China |
| 投稿时间：2024-03-07 修订日期：2024-04-07 |
| DOI：10.7643/issn.1672-9242.2024.04.016 |
| 中文关键词: 反应堆 一回路管道 材料老化 应力腐蚀开裂 不锈钢 溶解氧 氯离子浓度中图分类号:TG172 文献标志码:A 文章编号:1672-9242(2024)04-0135-05 |
| 英文关键词:reactor primary pipe material ageing stress corrosion crack stainless steel dissolved oxygen chloride ion concentration |
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| 中文摘要: |
| 2022年，法国电力公司(EDF)大量核电机组因一回路管道应力腐蚀开裂(SCC)问题而停堆检修，对法国甚至欧洲的生产生活造成巨大影响。针对该事件，在总结国内外核反应堆类似失效案例及材料老化研究成果的基础上，对反应堆不锈钢部件的SCC问题的机理、影响因素、抑制措施开展了分析，并结合我国核电机组服役时间逐渐延长，材料老化、设备失效问题日益突出的现状，提出我国核电运维改进措施，如优化残余应力、加强监督和检查，研发更有效的无损检测技术等。同时，探讨了我国在反应堆材料老化研究方面的发展方向。 |
| 英文摘要: |
| In 2022, a large amount of EDF nuclear power plants (NPP) were shut down because of stress corrosion crack (SCC) on primary pipe of reactor. It led enormous impact on industry and normal life in France and Europe. To understand this accident, the mechanism, effect factors and migration methods of SCC were analyzed on the basis of summarizing similar failure cases and material aging research results of nuclear reactors at home and abroad. Combined with the increasingly prominent problems such as the gradual extension of the service time, the aging of materials and equipment failure of nuclear power units in China, mitigation measures such as reduction of residual stress, improvement of inspection and development of advance nondestructive examination technologies were suggested. Also, the development direction of aging research on reactor materials in China was discussed. |
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