摘要
反应堆压力边界的核一级部件在设计中要求进行疲劳分析。当前国际上的研究结果表明,目前分析中使用的规范疲劳设计曲线在考虑冷却剂环境条件下并不保守,并引起了各国核电监管机构对此的广泛关注。文中介绍了各主要核电国家对冷却剂环境疲劳的研究情况,讨论了NRC关于冷却剂环境的疲劳分析方法以及ASME规范的后续进展。针对考虑环境疲劳后可能带来的一系列问题,提出了建议的解决方法。
It is required that the fatigue analysis should be done for nuclear reactor class 1 components composing of the reactor pressure boundary. Based on worldwide resear- ches, it is found that the fatigue design curves currently used in the analysis have no enough margins considering the coolant environmental effect, and the regulatory bodies in the world have paid high attention to it. General information related to the research background was introduced, and the NRC method and the related ASME activities were discussed. Possible ways are recommended to deal with the potential issues that may arise.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第11期2114-2119,共6页
Atomic Energy Science and Technology
基金
大型先进压水堆核电站重大专项资助项目(2010ZX06002)
关键词
反应堆
压力边界
疲劳设计曲线
冷却剂环境
监管机构
reactor
pressure boundary
fatigue design curve
coolant environment
regulatory body
