In this study, the residual stresses generated within the overlay-welded cladding and base material of reactor pressure vessel (RPV) steel were measured for as-welded and postwelded heat-treated conditions using the sectioning and deep-hole-drilling (DHD) techniques. In addition, thermo–elastic–plastic creep analyses considering the phase transformation in the heat-affected zone using the finite element method (FEM) were performed to evaluate the weld residual stress produced by overlay-welding and postweld heat treatment (PWHT). By comparing the analytical results with the experimentally determined values, we found a good agreement for the residual stress distribution within the cladding and the base material. The tensile residual stress in the cladding is largely due to the difference in the thermal expansion of the cladding and the base material. It was also shown that considering phase transformation during welding was important for improving the accuracy of the weld residual stress analysis. Using the calculated residual stress distribution, we performed fracture mechanics analyses for a vessel model with a postulated flaw during pressurized thermal shock (PTS) events. The effect of the weld residual stress on the structural integrity of RPVs was evaluated through some case studies. The results indicated that consideration of the weld residual stress produced by overlay-welding and PWHT is important for assessing the structural integrity of RPVs.
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October 2013
Research-Article
Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel
Hiroyuki Nishikawa,
Hiroyuki Nishikawa
1
1Present address: Mizuho Information & Research Institute, Inc., 2-3 Nishiki-cho, Kanda, Chiyoda-ku, Tokyo 101-8443, Japan.
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Mitsuyuki Nakamura,
Mitsuyuki Nakamura
2
2Present address: Research Organization for Information Science & Technology, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan.
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Kunio Onizawa
Kunio Onizawa
Nuclear Safety Research Center,
Japan Atomic Energy Agency
,2-4 Shirakata-shirane
,Tokai-mura, Naka-gun
,Ibaraki 319-1195
, Japan
Search for other works by this author on:
Kunio Onizawa
Nuclear Safety Research Center,
Japan Atomic Energy Agency
,2-4 Shirakata-shirane
,Tokai-mura, Naka-gun
,Ibaraki 319-1195
, Japan
1Present address: Mizuho Information & Research Institute, Inc., 2-3 Nishiki-cho, Kanda, Chiyoda-ku, Tokyo 101-8443, Japan.
2Present address: Research Organization for Information Science & Technology, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan.
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the Journal of Pressure Vessel Technology. Manuscript received July 23, 2012; final manuscript received May 19, 2013; published online September 16, 2013. Assoc. Editor: Xian-Kui Zhu.
J. Pressure Vessel Technol. Oct 2013, 135(5): 051402 (9 pages)
Published Online: September 16, 2013
Article history
Received:
July 23, 2012
Revision Received:
May 19, 2013
Citation
Katsuyama, J., Nishikawa, H., Udagawa, M., Nakamura, M., and Onizawa, K. (September 16, 2013). "Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel." ASME. J. Pressure Vessel Technol. October 2013; 135(5): 051402. https://doi.org/10.1115/1.4024617
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