RESEARCH ON WELD RESIDUAL STRESS OF DISSIMILAR STEEL WELD IN THICK-WALL PRESSURE PIPE OF NUCLEAR POWER PLANT BY THE FINITE ELEMENT SIMULATION METHOD

CHEN Mingya; YU Weiwei; HAN Yaolei; LIN Lei; PENG Qunjia; SHI Fangjie; ZHAO Wanxiang

doi:10.16579/j.issn.1001.9669.2025.08.007

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RESEARCH ON WELD RESIDUAL STRESS OF DISSIMILAR STEEL WELD IN THICK-WALL PRESSURE PIPE OF NUCLEAR POWER PLANT BY THE FINITE ELEMENT SIMULATION METHOD

·Experimental Research·Testing Technology· | 更新时间：2025-08-18

- RESEARCH ON WELD RESIDUAL STRESS OF DISSIMILAR STEEL WELD IN THICK-WALL PRESSURE PIPE OF NUCLEAR POWER PLANT BY THE FINITE ELEMENT SIMULATION METHOD
- Journal of Mechanical Strength Vol. 47, Issue 8, Pages: 59-65(2025)
- 作者机构：
  
  1.苏州热工研究院有限公司，苏州215004
  2.国家核电厂安全及可靠性工程技术研究中心，苏州215004
- 作者简介：
  
  PENG Qunjia, E-mail: qunjiapeng@163.com
- 基金信息：
  
  National Key Research & Development Program(2020YFB1901500);National Natural Science Foundation of China(12075274)
- DOI：10.16579/j.issn.1001.9669.2025.08.007
  CLC： TL351.6
- Received：22 December 2023，
  
  Revised：07 March 2024，
  
  Published：15 August 2025
- 稿件说明：
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陈明亚，余伟炜，韩姚磊，等 .核电厂厚壁承压管道异种钢焊缝的焊接残余应力数值仿真研究［J］. 机械强度，2025，47（8）：59-65.

CHEN Mingya，YU Weiwei，HAN Yaolei，et al. Research on weld residual stress of dissimilar steel weld in thick-wall pressure pipe of nuclear power plant by the finite element simulation method［J］. Journal of Mechanical Strength，2025，47（8）：59-65.
陈明亚，余伟炜，韩姚磊，等 .核电厂厚壁承压管道异种钢焊缝的焊接残余应力数值仿真研究［J］. 机械强度，2025，47（8）：59-65. DOI： 10.16579/j.issn.1001.9669.2025.08.007.

CHEN Mingya，YU Weiwei，HAN Yaolei，et al. Research on weld residual stress of dissimilar steel weld in thick-wall pressure pipe of nuclear power plant by the finite element simulation method［J］. Journal of Mechanical Strength，2025，47（8）：59-65. DOI： 10.16579/j.issn.1001.9669.2025.08.007.

摘要

压水堆核电厂反应堆压力容器（Reactor Pressure Vessel

RPV）、蒸汽发生器（Steam Generator

SG）、主泵等大型碳钢设备的容器管嘴与奥氏体钢管道通过异种钢焊缝（Dissimilar Metal Weld

DMW）相连接。厚壁DMW存在材料不均和较为复杂的焊接残余应力（Weld Residual Stress

WRS），容易导致疲劳或应力腐蚀裂纹的产生。首先，调研了国际上经测量和数值分析获得的核电厂DMW的WRS情况；其次，基于一种单元体的体积均匀加热的WRS快速仿真方法，获取了一回路热管段（RPV出口至SG进口之间的连接管段，其为一回路压力边界中运行参数最高的管段）DMW的WRS。数值仿真分析的结果与美国推荐的拟合包络曲线趋势一致，且整体上可以被美国推荐的拟合曲线包络，说明所述的WRS快速仿真方法是可行的。厚壁DMW的WRS数值较大，但在管道内、外表面位置处的应力值比美国的推荐值保守，表明在实际结构分析中可以获得更多的安全裕度。

Abstract

In pressurized-water reactor nuclear power plants

the vessel nozzles of large carbon steel equipment such as reactor pressure vessel (RPV)

steam generator (SG)

and main pumps are connected to austenitic steel pipes through dissimilar metal welds (DMWs). The thick-walled DMW has material inhomogeneity and complex weld residual stress (WRS)

which easily leads to the generation of fatigue or stress corrosion cracks.Firstly

the WRS of DMW in nuclear power plants obtained through international measurements and numerical analyses was investigated. Then

based on a rapid WRS simulation method for volume uniform heating of unit cells

the WRS of DMW in the hot leg of the primary loop (the connecting pipe section from RPV outlet to SG inlet

which is the pipe section with the highest operating parameters in the primary loop pressure boundary) was obtained.The numerical simulation results are consistent with the trend of the fitting envelope curve recommended by the United States

and the overall results can be enveloped by the fitting curve recommended by the United States

indicating that the described rapid WRS simulation method is feasible. The WRS of thick-walled DMW is relatively high

and the stress values at the inner and outer surfaces of the pipe are more conservative than the recommended values of the United States

suggesting that more safety margins can be obtained in actual structural analyses.

关键词

Keywords

references

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