钠冷快堆高温钠管道应力分析与评定  

Stress Analysis and Evaluation for High Temperature Pipe Lines of Sodium Cooled Fast Reactor

作　　者：董碧波[1] 

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《核电工程与技术》2006年第3期23-30,共8页Nuclear Power Engineering and Technology

摘　　要：本文简要介绍了RCC—MR标准的发展历程，简要说明了采用RCC—MR“RB3600管道设计标准”对高温钠管道进行应力分析与计算的步骤；作为实例，运用CASTEM2000计算程序对一个在工作寿期内承受高温热循环载荷的钠管道进行详细的应力分析与评定，以及在整个工作寿期内的总体应变和疲劳-蠕变分析。This paper presents a stress analysis and evaluation example for high temperature; sodium pipe of sodium cooled fast reactor. The mechanical calculations are, based on those analysis results. It introduces the rules of the RCC-MR and the program of CASTEM2000 used in stress calculation. The pipe analysis contains the type of damage, reactions of supports （dynamic load is not taken into account）, negligible creep or significant creep and creep-fatigue calculation according to the pipe＇s load and boundary conditions during the total period.

关 键 词：钠冷快堆 高温钠管道 应力分析 疲劳 蠕变 

分 类 号：TL411[核科学技术—核技术及应用]