CAJ | 학술논문

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N RC关于冷却剂环境的疲劳分析方法以及ASM E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。
반응퇴압력변계적핵일급부건재설계중요구진행피로분석。당전국제상적연구결과표명，목전분석중사용적규범피로설계곡선재고필냉각제배경조건하병불보수，병인기료각국핵전감관궤구대차적엄범관주。문중개소료각주요핵전국가대냉각제배경피로적연구정황，토론료N RC관우냉각제배경적피로분석방법이급ASM E규범적후속진전。침대고필배경피로후가능대래적일계렬문제，제출료건의적해결방법。
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 .