The applicability of miniature compact tension (Mini-C(T)) specimens to fracture toughness evaluation of neutron-irradiated reactor pressure vessel (RPV) steels was investigated. Three types of RPV steels neutron-irradiated to a high-fluence region were prepared and manufactured as Mini-C(T) specimens according to Japan Electric Association Code (JEAC) 4216-2015. Through careful selection of the test temperature by considering previously obtained mechanical properties data, valid fracture toughness, and reference temperature (To) was obtained with a relatively small number of specimens. Comparing the fracture toughness and To values determined using other larger specimens with those determined using the Mini-C(T) specimens, To values of both unirradiated and irradiated Mini-C(T) specimens were found to be the acceptable margin of error. The scatter of 1T-equivalent fracture toughness values of both unirradiated and irradiated materials obtained using Mini-C(T) specimens did not differ significantly from the values obtained using larger specimens. The correlation between the Charpy 41 J transition temperature (T41J) and the To values agreed very well with that of the data in the literature, regardless of specimen size and fracture toughness of the materials before irradiation. Based on these findings, it was concluded that Mini-C(T) specimens can be applied to fracture toughness evaluation of neutron-irradiated materials without significant specimen size dependence.
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October 2018
Research-Article
Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels
Yoosung Ha,
Yoosung Ha
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ha.yoosung@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ha.yoosung@jaea.go.jp
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Tohru Tobita,
Tohru Tobita
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: tobita.tohru@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: tobita.tohru@jaea.go.jp
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Takuyo Ohtsu,
Takuyo Ohtsu
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ohtsu.takuyo@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ohtsu.takuyo@jaea.go.jp
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Hisashi Takamizawa,
Hisashi Takamizawa
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: takamizawa.hisashi@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: takamizawa.hisashi@jaea.go.jp
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Yutaka Nishiyama
Yutaka Nishiyama
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp
Search for other works by this author on:
Yoosung Ha
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ha.yoosung@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ha.yoosung@jaea.go.jp
Tohru Tobita
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: tobita.tohru@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: tobita.tohru@jaea.go.jp
Takuyo Ohtsu
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ohtsu.takuyo@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: ohtsu.takuyo@jaea.go.jp
Hisashi Takamizawa
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: takamizawa.hisashi@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: takamizawa.hisashi@jaea.go.jp
Yutaka Nishiyama
Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp
Japan Atomic Energy Agency,
Shirakata 2-4, Tokai-mura,
Naka-gun 319-1195, Ibaraki-ken, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received February 8, 2018; final manuscript received June 14, 2018; published online August 2, 2018. Assoc. Editor: Yun-Jae Kim.
J. Pressure Vessel Technol. Oct 2018, 140(5): 051402 (6 pages)
Published Online: August 2, 2018
Article history
Received:
February 8, 2018
Revised:
June 14, 2018
Citation
Ha, Y., Tobita, T., Ohtsu, T., Takamizawa, H., and Nishiyama, Y. (August 2, 2018). "Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels." ASME. J. Pressure Vessel Technol. October 2018; 140(5): 051402. https://doi.org/10.1115/1.4040642
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