Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (3): 30606-030606.doi: 10.11889/j.0253-3219.2020.hjs.43.030606

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles    

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

Wei GONG1,2,Xiaochun ZHANG1,2(),Xiaoyan WANG1,2,Jingyi XUE1,2,Yuan FU1,2   

  1. 1.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    2.Innovative Academies in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China
  • Received:2019-12-10 Revised:2020-03-04 Online:2020-03-15 Published:2020-03-24
  • Contact: Xiaochun ZHANG E-mail:zhangxiaochun@sinap.ac.cn
  • About author:GONG Wei, female, born in 1988, graduated from Shanghai University with a master's degree in 2013, focusing on the structural integrity of nuclear reactor pressure piping
  • Supported by:
    Strategic Priority Research Program of Chinese Academy of Sciences(XDA02010000)

Abstract: 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.

Key words: TMSR-LF1, Pipe, PepS, Creep-fatigue, High temperature

CLC Number: 

  • TL353