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| 压水堆核电站不锈钢焊缝材料腐蚀疲劳模型 |
刘夏城1, 邹建荣2, 高良文3, 周龙4,5, 谭季波4, 吴欣强4, 张兹瑜4( ) |
1.三门核电有限公司 台州 317100
2.上海核工程研究设计院股份有限公司 上海 200233
3.国核示范电站有限责任公司 荣成 264300
4.中国科学院金属研究所 中国科学院核用材料与安全评价重点实验室 辽宁省核电材料安全与评价技术重点实验室 沈阳 110016
5.中国科学技术大学材料科学与工程学院 沈阳 110016 |
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| Corrosion Fatigue Model for Stainless Steel Weld Seam Used in Pressurized Water Reactor Nuclear Power Plants |
| LIU Xiacheng1, ZOU Jianrong2, GAO Liangwen3, ZHOU Long4,5, TAN Jibo4, WU Xinqiang4, ZHANG Ziyu4() |
1.Sanmen Nuclear Power, Taizhou 317100, China
2.Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
3.State Nuclear Power Demonstration Plant, Rongcheng 264300, China
4.CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
5.School of Materials Science and Engineering, University of Science and Technology of China, Shenyang 110016, China |
引用本文:
刘夏城, 邹建荣, 高良文, 周龙, 谭季波, 吴欣强, 张兹瑜. 压水堆核电站不锈钢焊缝材料腐蚀疲劳模型[J]. 中国腐蚀与防护学报, 2026, 46(5): 1613-1618.
Xiacheng LIU,
Jianrong ZOU,
Liangwen GAO,
Long ZHOU,
Jibo TAN,
Xinqiang WU,
Ziyu ZHANG.
Corrosion Fatigue Model for Stainless Steel Weld Seam Used in Pressurized Water Reactor Nuclear Power Plants[J]. Journal of Chinese Society for Corrosion and protection, 2026, 46(5): 1613-1618.
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