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CPR1000核电站核岛主管道预制焊接变形研究及应用 被引量:4

Research and application of the dynamic welding deformation in the prefabrication of CPR1000 reactor coolant piping(RCP)
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摘要 针对CPR1000核电站核岛主管道用厚壁不锈钢核岛主管道预制焊接中的焊接变形问题,采用理论分析与模拟试验相结合的研究方法,系统地研究了核电站核岛主管道预制焊接不同装配结构的焊接变形特点,确立了主管道预制焊接的反变形措施,保证了主管道预制焊接质量。 The article focused on the welding deforming issues of thick-walled stainless steel for reactor coolant piping(RCP) during the prefabrication,which be used in CPR1000 Project.By theoretical analysis combining with simulative test,the dynamic welding deforming characteristics of all kinds of welds in thick-walled stainless steel RCP prefabrication was studied systemically.An anti-deforming method for RCP prefabricating welding had been obtained,which ensured the welding quality of RCP successfully.
出处 《焊接技术》 北大核心 2011年第11期57-60,79,共4页 Welding Technology
关键词 奥氏体不锈钢 主管道 焊接 变形控制 austenitic stainless steel,reactor coolant piping(RCP),welding,deformation control
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  • 1王蕊,梁振新,张建勋.铝合金氩弧焊接角变形动态过程表征[J].焊接学报,2007,28(3):29-32. 被引量:6
  • 2Masubuchi K. Prediction and control of residual stresses and distortion in welded stroetures. Proe [C]. Theoretieal Prediction in Joining and Welding.Osaka,Japan,1996. 71-88.
  • 3Penso J A. Development of a PC-based FEM model to predict weld distortion[D].Master's Thesis. The Ohio State University, Columbus,Ohio,USA, 1992.
  • 4Deng Dean, Hidekazu Murakawa, Liang Wei. Numerical simulation of temperature field and residual stress in multi-pass welds in stainless steel pipe and comparison with experimental measurements[J].Computational Materials Science, 2006,37 : 269-277.
  • 5Deng Dean,Murakawa Hidekazu. Prediction of welding residual stress in multi-pass butt-welded modi-fied 9Cr-1 Mo steel pipe considering phase transformation effects[J].Computational Materials Science,2006,37:209-219.
  • 6Sattari-Far I,Javadi Y. Influence of welding sequence on welding distortions in pipes[J]. International Journal of Pressure Vessels and Piping,2007.
  • 7Erika Hedblom. Multipass welding of nuclear reactor components -measurements[D]. Lulea University of Technology:Department of Applied Physics and Mechanical Engineering,Division of ComputerAided Design.2002.
  • 8Xu Jijin,Chen Ligong,Ni Chunzhen. Effect of vibratoly weht conditioning on the residual stresses and distortion in muhipass girth-butt welded pipes [J]. International Journal of Pressure Vessels and Piping,2007,84:298-303.
  • 9Karllsson L. Thermal stresses in welding[C]. Thermal stresses I,Amsterdam, North-Holland, 1986. 299-389.

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