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中国腐蚀与防护学报  2018, Vol. 38 Issue (6): 511-516    DOI: 10.11902/1005.4537.2017.188
  本期目录 | 过刊浏览 |
核电材料高温高压水缺口疲劳性能研究现状与进展
廖家鹏1,2,吴欣强1()
1. 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
2. 中车株洲电力机车有限公司 大功率交流传动电力机车系统集成国家重点实验室 株洲 412001
Review of Notch Effect on Fatigue Behavior of Materials for LWR Plants in High Temperature High Pressure Water
Jiapeng LIAO1,2,Xinqiang WU1()
1. Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2. State Key Laboratory of Heavy Duty AC Drive Electric Locomotive Systems Integration, CRRC Zhuzhou Locomotive Co., Ltd., Zhuzhou 412001, China
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摘要: 

综述了轻水堆核电站用结构材料的缺口疲劳问题研究现状，分析了材料、应力、环境和缺口几何形状等影响因素，讨论了核电材料在高温高压水中缺口疲劳裂纹萌生及裂纹扩展的可能机理，指出了当前研究中存在的问题及进一步的研究方向。
关键词 ： 腐蚀疲劳,  轻水堆核电站,  缺口效应    
Abstract：

The effect of notch geometry on fatigue performance of structural materials for light water reactor plants was reviewed. Four factors affecting the fatigue behavior of notched specimen were taken into account, including characteristics of materials, stress state, corrosive environments and notch geometry. The possible mechanisms of fatigue crack initiation and propagation of notched specimen for nuclear-grade materials in high temperature high pressure water have been discussed. The coming possible research topics and directions are also proposed.
Key words： corrosion fatigue    light water reactor plant    notch effects
收稿日期: 2017-11-15     
ZTFLH:  TG172.8  
基金资助:国家科技重大专项专题(2017ZX06002003-004-002);中国科学院院重点部署项目(ZDRW-CN-2017-1);中国科学院金属研究所创新基金(SCJJ-2013-ZD-02)
通讯作者: 吴欣强     E-mail: xqwu@imr.ac.cn
Corresponding author: Xinqiang WU     E-mail: xqwu@imr.ac.cn
作者简介: 廖家鹏，男，1990年生，博士生
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廖家鹏,吴欣强. 核电材料高温高压水缺口疲劳性能研究现状与进展[J]. 中国腐蚀与防护学报, 2018, 38(6): 511-516.
Jiapeng LIAO, Xinqiang WU. Review of Notch Effect on Fatigue Behavior of Materials for LWR Plants in High Temperature High Pressure Water. Journal of Chinese Society for Corrosion and protection, 2018, 38(6): 511-516.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2017.188      或      https://www.jcscp.org/CN/Y2018/V38/I6/511

ClassificationTypical partConstruction material
Bolt holePressure vessel headStainless steel (SS)
Welding discontinuitiesPressure vessel, SG tubes, pressurizer, small-diameter pipelinesAlloy 690/52 or 152
Primary loop circulation piping system, reactor internalsSS/Ni-based alloy
Pressure vessel, SG safe-end welds, pressurizerSS/ Ni-based alloy/Low alloy steel
Pressure vesselButt welding of low alloy steel
表1  LWR核电站涉及的几何不连续典型部位及其结构材料
Influencing factorTesting environment
Material: Composition, microstructure, inclusions, surface stateRT air, LWR water
Notch geometry: Notch type, notch angle, notch depth, notch root radiusRT air, LWR water
Stress state: Stress amplitude, stress rate, wave formRT air, LWR water
Environment: Temperature, pressure, pH, DO, DHLWR water
表2  LWR水环境中和室温空气中缺口疲劳性能的主要影响因素
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