反应堆冷却剂系统辅助管道缺陷焊缝疲劳分析与评价

Fatigue Analysis and Assessments of Flawed Welds for Auxiliary Piping of Reactor Coolant System

  • 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。

     

    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 reactor operation in five years with that specified in detail design phase was taken, the fatigue analysis and assessment for the typical flawed weld were performed using the optimized fatigue method. The assessment results show that the fatigue failure of the auxiliary piping weld will not occur in ten years operation of nuclear power plant.

     

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