期刊文献+

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 被引量:1

Research on weld residual stress of dissimilar steel weld in thick-wall pressure pipe of nuclear power plant by the finite element simulation method
在线阅读 下载PDF
导出
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。 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.
作者 陈明亚 余伟炜 韩姚磊 林磊 彭群家 史芳杰 赵万祥 CHEN Mingya;YU Weiwei;HAN Yaolei;LIN Lei;PENG Qunjia;SHI Fangjie;ZHAO Wanxiang(Suzhou Nuclear Power Research Institute Co.,Ltd.,Suzhou 215004,China;National Nuclear Power Plant Safety and Reliability Engineering Research Center,Suzhou 215004,China)
出处 《机械强度》 北大核心 2025年第8期59-65,共7页 Journal of Mechanical Strength
基金 国家重点研发计划项目(2020YFB1901500) 国家自然科学基金项目(12075274)。
关键词 压水堆 异种钢焊缝 焊接残余应力 数值分析 Pressurized-water reactor Dissimilar steel weld Weld residual stress Numerical simulation
  • 相关文献

参考文献2

二级参考文献19

共引文献4

同被引文献14

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部