| 注册
首页|期刊导航|压力容器|反应堆压力容器内环形件焊接过程数值分析

反应堆压力容器内环形件焊接过程数值分析

孙少南 于敦吉 邱阳 董元元 陈旭

压力容器2016,Vol.33Issue(11):24-32,9.
压力容器2016,Vol.33Issue(11):24-32,9.DOI:10.3969/j.issn.1001-4837.2016.11.005

反应堆压力容器内环形件焊接过程数值分析

Finite Element Simulation on Welding Process of Nuclear Reactor Pressure Vessel′s Inner Ring

孙少南 1于敦吉 1邱阳 2董元元 2陈旭1

作者信息

  • 1. 天津大学 化工学院,天津 300354
  • 2. 中国核动力研究设计院,四川 成都 610000
  • 折叠

摘要

Abstract

The welding process of the inner ring of nuclear reactor pressure vessel was performed by finite element simulation and the distribution of welding residual stress was investigated. Compared with the 3D model,the 2D axisymmetric model can reflect the distribution of welding residual stress very well,and it can also improve the computational efficiency. Based on the axisymmetric model,the effect of the lumped-pass method and welding sequence on the residual stress were discussed. The results showed that lumped-pass method could both guarantee the accuracy and efficiency of the simulation. The stress was at a low level when the asymmetric groove and three times welding were conducted. These conclusions could pro-vide a reference for the design of the nuclear reactor pressure vessel.

关键词

反应堆/残余应力/轴对称模型/焊道集中/焊接顺序

Key words

reactor pressure vessel/residual stress/axisymmetric model/lumped-pass method/welding se-quence

分类

机械制造

引用本文复制引用

孙少南,于敦吉,邱阳,董元元,陈旭..反应堆压力容器内环形件焊接过程数值分析[J].压力容器,2016,33(11):24-32,9.

基金项目

国家自然科学基金重点项目(51435012) (51435012)

压力容器

OACSTPCD

1001-4837

访问量0
|
下载量0
段落导航相关论文