In recent years, the occurrence of primary water stress corrosion cracking (PWSCC) in Alloy 600 weld regions of PWR plants has increased. In order to evaluate the crack propagation of PWSCC, it is required to estimate stress distribution including residual stress and operational stress through the wall thickness of the Alloy 600 weld region. In a national project in Japan for the purpose of establishing residual stress evaluation method, a test model was produced using the same fabrication process in Japanese PWR plants in order to measure stress distribution change of the Alloy 132 weld region during fabrication process such as a hydrostatic test, welding a main coolant pipe to the stainless steel safe end and operation condition test. For the mock up test model, the stress distribution of selected fabrication processes was measured using the Deep Hole Drilling (DHD) method. From the measurement results, it was found that the stress distribution in thickness direction at the center of the Alloy 132 weld line was hardly varied with the hydrostatic test at site and operating condition test history. FE analysis was performed to calculate the stress distributions for each fabrication process. Comparing with measurement results, the validity of the FE analysis was confirmed. From the validation procedure, a standard residual stress evaluation method was established.
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ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping
ISBN:
978-0-7918-4369-7
PROCEEDINGS PAPER
Residual Stress Evaluation of Dissimilar Weld Joint Using Reactor Vessel Outlet Nozzle Mock-Up Model: Report 2
Naoki Ogawa,
Naoki Ogawa
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
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Itaru Muroya,
Itaru Muroya
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
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Youichi Iwamoto,
Youichi Iwamoto
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
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Kiminobu Hojo,
Kiminobu Hojo
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
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Kazuo Ogawa,
Kazuo Ogawa
Japan Nuclear Energy Safety Organization, Tokyo, Japan
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David J. Smith
David J. Smith
University of Bristol, Bristol, UK
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Naoki Ogawa
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
Itaru Muroya
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
Youichi Iwamoto
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
Kiminobu Hojo
Mitsubishi Heavy Industries, Ltd., Takasago, Japan
Kazuo Ogawa
Japan Nuclear Energy Safety Organization, Tokyo, Japan
Ed Kingston
VEQTER Ltd., Bristol, UK
David J. Smith
University of Bristol, Bristol, UK
Paper No:
PVP2009-77269, pp. 353-364; 12 pages
Published Online:
July 9, 2010
Citation
Ogawa, N, Muroya, I, Iwamoto, Y, Hojo, K, Ogawa, K, Kingston, E, & Smith, DJ. "Residual Stress Evaluation of Dissimilar Weld Joint Using Reactor Vessel Outlet Nozzle Mock-Up Model: Report 2." Proceedings of the ASME 2009 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication, Parts A and B. Prague, Czech Republic. July 26–30, 2009. pp. 353-364. ASME. https://doi.org/10.1115/PVP2009-77269
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