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反应堆冷却剂系统辅助管道缺陷焊缝疲劳分析与评价
引用本文:臧峰刚,王伟,刘文进,张毅雄,曾忠秀,杨凯,邹鸣中. 反应堆冷却剂系统辅助管道缺陷焊缝疲劳分析与评价[J]. 原子能科学技术, 2008, 42(Z2)
作者姓名:臧峰刚  王伟  刘文进  张毅雄  曾忠秀  杨凯  邹鸣中
作者单位:中国核动力研究设计院,核反应堆系统设计技术国家级重点实验室,四川,成都,610041
摘    要:根据某核电厂反应堆冷却剂系统辅助管道核1级焊缝的在役检查结果和施工设计阶段应力分析结果,确定了疲劳分析与评价的典型缺陷焊缝.依据WRC502的实验结果和RCC-M规范,提出了用于疲劳分析的含热(微)裂纹效应的疲劳曲线.在此基础上,对机组运行5 a的瞬变统计次数与设计瞬态次数进行了对比研究,采用优化疲劳分析方法对典型缺陷焊缝进行了疲劳分析与评价.评价结果表明:辅助管道核1级焊缝在核电厂运行10 a内不会发生疲劳失效.

关 键 词:热(微)裂纹  管道  焊缝  疲劳

Fatigue Analysis and Assessments of Flawed Welds for Auxiliary Piping of Reactor Coolant System
ZANG Feng-gang,WANG Wei,LIU Wen-jin,ZHANG Yi-xiong,ZENG Zhong-xiu,YANG Kai,ZOU Ming-zhong. Fatigue Analysis and Assessments of Flawed Welds for Auxiliary Piping of Reactor Coolant System[J]. Atomic Energy Science and Technology, 2008, 42(Z2)
Authors:ZANG Feng-gang  WANG Wei  LIU Wen-jin  ZHANG Yi-xiong  ZENG Zhong-xiu  YANG Kai  ZOU Ming-zhong
Affiliation:ZANG Feng-gang,WANG Wei,LIU Wen-jin,ZHANG Yi-xiong,ZENG Zhong-xiu,YANG Kai,ZOU Ming-zhong(State Key Laboratory of Reactor System Design Technology,Nuclear Power Institute of China,Chengdu 610041,China)
Abstract:Based on the results from the in-service inspection to the auxiliary piping welds of reactor coolant system in a nuclear power plant and the corresponding stress analysis reports in detail design phase,the typical flawed welds were determined to take fatigue analysis and assessments in this paper.According to the experimental results from WRC 502 and RCC-M code,the fatigue curve for considering the microfissure effects was present.Furthermore,the comparison of the transient cycle numbers recorded in the rea...
Keywords:microfissure  piping  weld  fatigue  
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