基于PepS的高温核一级管道蠕变疲劳分析方法研究  

Application of PepS in creep-fatigue damage evaluation for class 1 nuclear piping at elevated temperature

作　　者：龚玮[1,2] 张小春 王晓艳[1,2] 薛静怡 傅远[1,2] GONGWei;ZHANG Xiaochun;WANG Xiaoyan;XUE Jingyi;FU Yuan(Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China;Innovative Academies in TMSR Energy System,Chinese Academy of Sciences,Shanghai 201800,China)

机构地区：[1]中国科学院上海应用物理研究所,上海201800 [2]中国科学院先进核能创新研究院,上海201800

出　　处：《核技术》2020年第3期87-94,共8页Nuclear Techniques

基　　金：中国科学院战略先导专项(No.XDA02010000)资助~~

摘　　要：钍基熔盐堆(Thorium Molten Salt Reactor-Liquid Fuel,TMSR-LF1)回路管道最高运行温度达650℃,高温服役下的管道蠕变-疲劳损伤分析及评定至关重要。目前仅ASME-BPVC-III-5-HBB规范中有适用于高温核一级管道的蠕变-疲劳损伤暂行评定方法,但该方法对于复杂管道系统使用起来过于繁琐。本文旨在使用管道分析软件PepS软件实现高温核一级复杂管系的分析与结构完整性评估。首先结合管道结构在多种载荷组合作用下的截面应力状态解析解,进行管道截面应力分析及应力线性化,并将结果与有限元数值解进行对比分析,两者的误差结果基本一致。随后,利用PepS软件对TMSR-LF1回路管道进行了力学分析和结构完整性评估,结其蠕变疲劳损伤结果位于包络线以内,满足蠕变疲劳极限的要求。该研究将管道分析软件与ASME评定规范进行了有效衔接,明确了评定方法,实现了高温核一级复杂管系的蠕变疲劳评估。[Background] The pipe of thorium molten salt reactor-liquid fuel(TMSR-LF1) has been designed to operate at 650 ℃ for a long time, therefore, it is extremely important to analyze its creep-fatigue damage. At present,the provisional creep-fatigue damage evaluation is only stipulated in ASME-BPVC-III-5-HBB, and the evaluation is too cumbersome to realize for complex piping systems. [Purpose] This study aims to apply PepS to analysis and evaluate class 1 nuclear piping at elevated temperature. [Methods] The analytical predictions of stress components and associated linearization of stress results through wall thickness of the pipe paths were successfully benchmarked with those given by finite element analysis(FEA), and good matching results was obtained. Finally, the structural analysis and structural integrity assessment procedures for the design structure of TMSR-LF1 on PepS are performed.[Conclusions] The study establishes effective connection between the ASME evaluate method and the pipe analysis software and clarifies the evaluation method. Hence, the creep-fatigue evaluation of class 1 nuclear complex piping system at elevated temperature is realized.

关 键 词：TMSR-LF1 管道 PepS 蠕变-疲劳 高温 

分 类 号：TL353[核科学技术—核技术及应用]