Welding is a commonly used and one of the most important material-joining processes in industry. The incidences of defects had been located by ultrasonic testing (UT) in various pressurizer nozzle dissimilar metal welds (DMW) at nuclear power plants. In order to evaluate the crack propagation, it is required to calculate the stress distribution including weld residual stress and operational stress through the wall thickness in the weld region. The analysis procedure in this paper included not only the pass-by-pass welding steps, but also other essential fabrication steps of surge, safety/relief and spray nozzles. In this paper, detailed welding simulation analyses have been conducted to predict the magnitude of these stresses in the weld material. To prevent primary water stress corrosion cracking (PWSCC) in pressurized water reactors (PWR) on susceptible welded pipes with dissimilar metal welds, the weld overlay process has been applied to repair nuclear reactor pipe joints in plants. The objectives of such repairs are to induce compressive axial residual stresses on the pipe inside surface, as well as increase the pipe thickness with a weld material that is not susceptible to stress-corrosion cracking. Hence, understanding the residual stress distribution is important to evaluate the reliability of pipe joints with weld overlay repairs. The finite element results in this paper showed that, after deposition of the DMW nozzle and stainless steel welds, tensile weld residual stresses still exist at regions of the DMW through the thickness. This tensile weld residual stress region was significantly reduced after welding the overlay. The overlay weld also provides a more uniform and large compressive region through the thickness which has a beneficial effect on the structural integrity of the DMW nozzle welds in the plant.
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ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
July 18–22, 2010
Bellevue, Washington, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-49255
PROCEEDINGS PAPER
Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles
Tao Zhang,
Tao Zhang
Engineering Mechanics Corporation of Columbus, Columbus, OH
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Bud Brust,
Bud Brust
Engineering Mechanics Corporation of Columbus, Columbus, OH
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Gery Wilkowski,
Gery Wilkowski
Engineering Mechanics Corporation of Columbus, Columbus, OH
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Sam Ranganath,
Sam Ranganath
XGEN Engineering, San Jose, CA
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Lihua Wang,
Lihua Wang
Industrial Technology Research Institute, Hsinchu, Taiwan
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Yao Long Tsai,
Yao Long Tsai
Industrial Technology Research Institute, Hsinchu, Taiwan
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Chin-Cheng Huang,
Chin-Cheng Huang
Institute of Nuclear Energy Research, Longtan, Taoyuan, Taiwan
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Ru-Feng Liu
Ru-Feng Liu
Institute of Nuclear Energy Research, Longtan, Taoyuan, Taiwan
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Tao Zhang
Engineering Mechanics Corporation of Columbus, Columbus, OH
Bud Brust
Engineering Mechanics Corporation of Columbus, Columbus, OH
Gery Wilkowski
Engineering Mechanics Corporation of Columbus, Columbus, OH
Sam Ranganath
XGEN Engineering, San Jose, CA
Lihua Wang
Industrial Technology Research Institute, Hsinchu, Taiwan
Yao Long Tsai
Industrial Technology Research Institute, Hsinchu, Taiwan
Chin-Cheng Huang
Institute of Nuclear Energy Research, Longtan, Taoyuan, Taiwan
Ru-Feng Liu
Institute of Nuclear Energy Research, Longtan, Taoyuan, Taiwan
Paper No:
PVP2010-25331, pp. 1333-1342; 10 pages
Published Online:
January 10, 2011
Citation
Zhang, T, Brust, B, Wilkowski, G, Ranganath, S, Wang, L, Tsai, YL, Huang, C, & Liu, R. "Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B. Bellevue, Washington, USA. July 18–22, 2010. pp. 1333-1342. ASME. https://doi.org/10.1115/PVP2010-25331
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