压水堆机组一回路环境促进疲劳分析方法研究  

Research on Environmentally Assisted Fatigue Analysis Method for Primary Circuit of Pressurized Water Reactor Units

作　　者：吕方明 姜赫 童赫 曹国畅 曹洪胜 Lyu Fangming;Jiang He;Tong He;Cao Guochang;Cao Hongsheng(China Nuclear Power Operation Technology Corporation,Ltd.,Wuhan,430223,China;CNNP Operation Maintenance Technology Co.,Ltd.,Hangzhou,311200,China)

机构地区：[1]中核武汉核电运行技术股份有限公司,武汉430223 [2]中核运维技术有限公司,杭州311200

出　　处：《核动力工程》2024年第6期232-236,共5页Nuclear Power Engineering

摘　　要：环境促进疲劳(EAF)是以水为冷却剂的反应堆的重要老化机理,对核电厂一回路关键敏感部位的疲劳寿命有重要影响。介绍了美国关于EAF关键敏感部位的筛选流程和环境疲劳修正因子(F_(en))的计算公式,并统计了美国延寿机组EAF关键敏感部位筛选的结果。参考美国EAF分析方法,筛选出了国内某核电厂1、2号机组一回路EAF关键敏感部位。所述流程、方法和案例对于国内核电厂EAF分析具有重要的指导和示范意义。Environmentally assisted fatigue(EAF)is an important aging mechanism for reactors with water as coolant,which has significant influences on the fatigue life of critical sensitive components in primary circuit of nuclear power plants.In this paper,the EAF screening process of critical sensitive components and the calculation formula of environmental fatigue correction factor(F_(en))deriving from the United States are introduced.Meanwhile,the results of EAF key sensitive part screening for the license renewal units in the United States are statistically analyzed.Referring to the EAF analysis method of the United States,the critical sensitive components of the primary circuit of Units 1 and 2 in a domestic plant are selected.The processes,methods,and cases have important guiding and demonstration significance for EAF analysis in the domestic nuclear power plants.

关 键 词：核电 环境促进疲劳(EAF) 筛选 老化 

分 类 号：TM623[电气工程—电力系统及自动化] TL48[核科学技术—核技术及应用]