We conducted fracture toughness testing on five types of commercially manufactured steel with different ductile-to-brittle transition temperatures. This was performed using specimens of different sizes and shapes, including the precracked Charpy-type (PCCv), 0.4T-CT, 1T-CT, and miniature compact tension specimens (0.16T-CT). Our objective was to investigate the applicability of 0.16T-CT specimens to fracture toughness evaluation by the master curve method for reactor pressure vessel (RPV) steels. The reference temperature (To) values determined from the 0.16T-CT specimens were overall in good agreement with those determined from the 1T-CT specimens. The scatter of the 1T-equivalent fracture toughness values obtained from the 0.16T-CT specimens was equivalent to that obtained from the other larger specimens. Furthermore, we examined the loading rate effect on To for the 0.16T-CT specimens within the quasi-static loading range prescribed by ASTM E1921. The higher loading rate gave rise to a slightly higher To, and this dependency was almost the same for the larger specimens. We suggested an optimum test temperature on the basis of the Charpy transition temperature for determining To using the 0.16T-CT specimens.
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October 2015
Research-Article
Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
Tohru Tobita,
Tohru Tobita
Nuclear Safety Research Center,
e-mail: tobita.tohru@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: tobita.tohru@jaea.go.jp
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Yutaka Nishiyama,
Yutaka Nishiyama
Nuclear Safety Research Center,
e-mail: nishiyama.yutaka93@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp
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Takuyo Ohtsu,
Takuyo Ohtsu
Nuclear Safety Research Center,
e-mail: ohtsu.takuyo@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: ohtsu.takuyo@jaea.go.jp
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Makoto Udagawa,
Makoto Udagawa
Nuclear Safety Research Center,
e-mail: udagawa.makoto@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: udagawa.makoto@jaea.go.jp
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Jinya Katsuyama,
Jinya Katsuyama
Nuclear Safety Research Center,
e-mail: katsuyama.jinya@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: katsuyama.jinya@jaea.go.jp
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Kunio Onizawa
Kunio Onizawa
Nuclear Safety Research Center,
e-mail: onizawa.kunio@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: onizawa.kunio@jaea.go.jp
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Tohru Tobita
Nuclear Safety Research Center,
e-mail: tobita.tohru@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: tobita.tohru@jaea.go.jp
Yutaka Nishiyama
Nuclear Safety Research Center,
e-mail: nishiyama.yutaka93@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp
Takuyo Ohtsu
Nuclear Safety Research Center,
e-mail: ohtsu.takuyo@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: ohtsu.takuyo@jaea.go.jp
Makoto Udagawa
Nuclear Safety Research Center,
e-mail: udagawa.makoto@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: udagawa.makoto@jaea.go.jp
Jinya Katsuyama
Nuclear Safety Research Center,
e-mail: katsuyama.jinya@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: katsuyama.jinya@jaea.go.jp
Kunio Onizawa
Nuclear Safety Research Center,
e-mail: onizawa.kunio@jaea.go.jp
Japan Atomic Energy Agency
,Shirakata-shirane 2-4, Tokai-mura
,Naka-gun, Ibaraki-ken 319-1195
, Japan
e-mail: onizawa.kunio@jaea.go.jp
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received October 6, 2014; final manuscript received December 14, 2014; published online February 27, 2015. Assoc. Editor: David L. Rudland.
J. Pressure Vessel Technol. Oct 2015, 137(5): 051405 (8 pages)
Published Online: October 1, 2015
Article history
Received:
October 6, 2014
Revision Received:
December 14, 2014
Online:
February 27, 2015
Citation
Tobita, T., Nishiyama, Y., Ohtsu, T., Udagawa, M., Katsuyama, J., and Onizawa, K. (October 1, 2015). "Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens." ASME. J. Pressure Vessel Technol. October 2015; 137(5): 051405. https://doi.org/10.1115/1.4029428
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