| 核级不锈钢高温水腐蚀疲劳机制及环境疲劳设计模型 |
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| 引用本文： | 吴欣强,徐松,韩恩厚,柯伟.核级不锈钢高温水腐蚀疲劳机制及环境疲劳设计模型[J].金属学报,2011(7):790-796. |
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| 作者姓名： | 吴欣强 徐松 韩恩厚 柯伟 |
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| 作者单位： | 中国科学院金属研究所金属腐蚀与防护国家重点实验室;中国科学院金属研究所辽宁省核电材料安全与评价技术重点实验室; |
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| 基金项目： | 国家重点基础研究发展计划项目2011CB610506; 国家科技重大专项项目2011ZX06004-009资助~~ |
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| 摘 要： | 通过模拟核电高温高压循环水腐蚀疲劳实验,研究了国产核级不锈钢的环境疲劳损伤行为与失效机制;评价了影响不锈钢高温高压水疲劳寿命的环境和载荷等因素,建立了一个植入环境损伤效应的疲劳设计模型,给出了便于工程应用的核级不锈钢的环境疲劳设计曲线.
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| 关 键 词： | 核级不锈钢 高温高压水 腐蚀疲劳 环境致裂 设计模型 |
CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL |
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| WU Xinqiang,XU Song State Key Laboratory for Corrosion , Protection.CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL[J].Acta Metallurgica Sinica,2011(7):790-796. |
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| Authors: | WU Xinqiang XU Song State Key Laboratory for Corrosion Protection |
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| Affiliation: | WU Xinqiang~(1,2)),XU Song~(1,HAN En-Hou~(1,KE Wei~(1,2)) 1) State Key Laboratory for Corrosion and Protection,Institute of Metal Research,Chinese Academy of Sciences,Shenyang 110016 2) Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Material,Shenyang 110016 |
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| Abstract: | The high safety of light water reactor nuclear power plants(NPPs) requires very strict design standard and service property of pressure boundary components materials.The service degradation and life assessment of the components materials primarily depend on the understanding of environmentally assisted failure mechanism,accumulation of service property data and construction of evaluation models.Currently domestic NPPs are relying on foreign design,operation and life assessment standards.However,recent exper... |
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| Keywords: | nuclear-grade stainless steel high temperature pressurized water corrosion fatigue environmentally assisted cracking design model |
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