In order to provide the technical basis for the judgment of the needs of surveillance specimens of heat-affected zone (HAZ) in reactor pressure vessel (RPV) steels, we performed a research on the characterization of metallurgical and mechanical properties of the HAZ in RPV steels. The distributions of grain size and phases were drawn as a map based on temperature histories around HAZ obtained from welding simulation. Referring to the HAZ map, typical HAZ materials were made by simulating temperature histories including postweld heat treatment (PWHT) within the HAZ. Metallurgical and mechanical characteristics for those HAZ materials were compared with those of base metal. From the results, it is clear that mechanical properties of HAZ materials depend not on the prior austenitic grain size but mostly on the phases. Concerning on the fracture toughness in HAZ, HAZ materials close to weld metal indicated higher toughness than that of base metal due to mixed structure of martensite and lower-bainite, while HAZ materials close to base metal were equivalent or slightly lower toughness than that of base metal due to the same phase as base metal of upper-bainite.
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June 2012
Materials And Fabrication
Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel
Jinya Katsuyama,
Jinya Katsuyama
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195
Japan
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Tohru Tobita,
Tohru Tobita
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195
Japan
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Yutaka Nishiyama,
Yutaka Nishiyama
Nuclear Safety Research Center, Japan Atomic Energy Agency, 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
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Jinya Katsuyama
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195
Japan
Tohru Tobita
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195
Japan
Yutaka Nishiyama
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195
Japan
Kunio Onizawa
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195
Japan
J. Pressure Vessel Technol. Jun 2012, 134(3): 031402 (7 pages)
Published Online: May 18, 2012
Article history
Received:
October 6, 2010
Revised:
November 11, 2011
Published:
May 17, 2012
Online:
May 18, 2012
Citation
Katsuyama, J., Tobita, T., Nishiyama, Y., and Onizawa, K. (May 18, 2012). "Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel." ASME. J. Pressure Vessel Technol. June 2012; 134(3): 031402. https://doi.org/10.1115/1.4005868
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