核安全设备疲劳分析方法与步骤  

Method and Procedure of Fatigue Analysis for Nuclear Equipment

作　　者：文静[1] 房永刚[1] 路燕[1] 邹鸣中[2] 张跃[1] 孙造占[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082 [2]中国核动力研究设计院,四川成都610041

出　　处：《原子能科学技术》2014年第1期121-126,共6页Atomic Energy Science and Technology

基　　金：国家科技重大专项资助项目(2011ZX06002-010)

摘　　要：以某核电厂稳压器上封头为例,采用ANSYS有限元分析软件,考虑两个有代表性的温度和压力瞬态,同时考虑地震的影响,采用RCC-M规范,进行了疲劳分析,详细说明了核安全设备疲劳分析的方法和步骤。本文为核安全设备及管道系统的疲劳分析与评价提供了参考。As an example ,the fatigue analysis for the upper head of the pressurizer in one NPP was carried out by using ANSYS ,a finite element method analysis software . According to RCC-M code ,only two kinds of typical transients of temperature and pres-sure were considered in the fatigue analysis .Meanwhile ,the influence of earthquake was taken into account .The method and procedure of fatigue analysis for nuclear safety equipment were described in detail .This paper provides a reference for fatigue analysis and assessment of nuclear safety grade equipment and pipe .

关 键 词：核电厂 稳压器 疲劳分析 

分 类 号：TL353[核科学技术—核技术及应用]