Analysis and Discussion for Fast Fracture of Reactor Pressure Vessel （RPV） Based on RCC-M Code
-
摘要: 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。Abstract: The fast fracture analysis and evaluation methods were compared and discussed in appendix ZG of RCC-M code Ver.2000 and Ver.2007. Comparison shows that the appendix ZG 2007 edition has a wider scope of application, the process of analysis in Ver.2007 is relatively simplified and the consideration in Ver.2007 are more comprehensive for the material aging. Taking the analysis of the fast fracture of the reactor core as an example, the sensitivity of the orientation parameters of the reference defects is analyzed, and the evaluation results of the two versions were compared. The results show that the margin of the evaluation results of Ver.2007 appendix ZG is much larger and the limitation of the P-T curve of the reactor pressure vessel is enlarged, and the operation space of the nuclear power plant is expanded
-
Key words:
- RCC-M code /
- Analysis for fast fracture /
- Reactor pressure vessel
-
计量
- 文章访问数: 14
- HTML全文浏览量: 5
- PDF下载量: 0
- 被引次数: 0
下载:
