Primary water stress corrosion cracking (PWSCC) phenomenon in dissimilar metal welds is one of the safety issues in ageing pressurized water reactor (PWR) piping systems. It is well known that analysis accuracy of cracking propagation due to PWSCC depends on welding residual stress conditions. The U.S. Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) carried out an international round robin validation program to evaluate and quantify welding residual stress analysis accuracy and uncertainty. In this paper, participation results of the authors in the round robin program were reported. The three-dimensional (3D) analysis based on a fast weld simulation using an iterative substructure method (ISM), was shown to provide accurate results in a high-speed computation. Furthermore, the influence of different heat source models on analysis results was investigated. It was demonstrated that the residual stress and distortion calculated using the moving heat source model were more accurate.
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April 2016
Research-Article
Prediction of Weld Residual Stress in a Pressurized Water Reactor Pressurizer Surge Nozzle
Akira Maekawa,
Akira Maekawa
Institute of Nuclear Safety System, Inc.,
64 Sata, Mihama-cho,
Mikata-gun, Fukui 919-1205, Japan
e-mail: maekawa@inss.co.jp
64 Sata, Mihama-cho,
Mikata-gun, Fukui 919-1205, Japan
e-mail: maekawa@inss.co.jp
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Atsushi Kawahara,
Atsushi Kawahara
Joining and Welding Research Institute,
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: Kawahara@jwri.osaka-u.ac.jp
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: Kawahara@jwri.osaka-u.ac.jp
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Hisashi Serizawa,
Hisashi Serizawa
Joining and Welding Research Institute,
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: serizawa@jwri.osaka-u.ac.jp
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: serizawa@jwri.osaka-u.ac.jp
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Hidekazu Murakawa
Hidekazu Murakawa
Joining and Welding Research Institute,
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: murakawa@jwri.osaka-u.ac.jp
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: murakawa@jwri.osaka-u.ac.jp
Search for other works by this author on:
Akira Maekawa
Institute of Nuclear Safety System, Inc.,
64 Sata, Mihama-cho,
Mikata-gun, Fukui 919-1205, Japan
e-mail: maekawa@inss.co.jp
64 Sata, Mihama-cho,
Mikata-gun, Fukui 919-1205, Japan
e-mail: maekawa@inss.co.jp
Atsushi Kawahara
Joining and Welding Research Institute,
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: Kawahara@jwri.osaka-u.ac.jp
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: Kawahara@jwri.osaka-u.ac.jp
Hisashi Serizawa
Joining and Welding Research Institute,
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: serizawa@jwri.osaka-u.ac.jp
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: serizawa@jwri.osaka-u.ac.jp
Hidekazu Murakawa
Joining and Welding Research Institute,
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: murakawa@jwri.osaka-u.ac.jp
Osaka University,
11-1 Mihogaoka,
Ibaraki, Osaka 567-0047, Japan
e-mail: murakawa@jwri.osaka-u.ac.jp
1Corresponding author.
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received December 1, 2014; final manuscript received August 11, 2015; published online October 6, 2015. Assoc. Editor: Xian-Kui Zhu.
J. Pressure Vessel Technol. Apr 2016, 138(2): 021401 (11 pages)
Published Online: October 6, 2015
Article history
Received:
December 1, 2014
Revised:
August 11, 2015
Citation
Maekawa, A., Kawahara, A., Serizawa, H., and Murakawa, H. (October 6, 2015). "Prediction of Weld Residual Stress in a Pressurized Water Reactor Pressurizer Surge Nozzle." ASME. J. Pressure Vessel Technol. April 2016; 138(2): 021401. https://doi.org/10.1115/1.4031376
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