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.
Prediction of Weld Residual Stress in a Pressurized Water Reactor Pressurizer Surge Nozzle
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.
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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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