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对2000版和2007版RCC-M附录ZG中的快速断裂分析评价方法进行对比分析。结果表明:2007版附录ZG的适用范围更广,分析评价过程相对简化,对材料老化的考虑也更加全面。以堆芯筒体段的快速断裂分析评价为例,对基准裂纹的方位参数进行敏感性分析,将2个版本的评价结果进行对比。结果表明:采用2007版附录ZG得到的评价结果安全裕量更大,同时增大了反应堆压力容器压力-温度(P-T)曲线的限制范围,扩大了核电厂运行操作空间。
Comparative analysis of rapid fracture analysis methods in the 2000 and 2007 RCC-M Appendix ZG was performed. The results show that the application of the 2007 edition of ZG is more extensive, the analysis and evaluation process is relatively simplified, and the consideration of material aging is more comprehensive. Taking the rapid fracture analysis and evaluation of the core barrel segment as an example, the sensitivity analysis of the orientation crack of the reference crack is carried out, and the evaluation results of the two versions are compared. The results show that the evaluation results obtained with the 2007 Appendix ZG have a larger safety margin and a larger limit of the pressure-temperature (P-T) curve of the reactor pressure vessel, expanding the operating space for nuclear power plants.