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Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels

[+] Author and Article Information
Yoosung Ha

Nuclear Safety Research Center, Japan Atomic Energy Agency, Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan
ha.yoosung@jaea.go.jp

Tohru Tobita

Nuclear Safety Research Center, Japan Atomic Energy Agency, Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan
tobita.tohru@jaea.go.jp

Takuyo Ohtsu

Nuclear Safety Research Center, Japan Atomic Energy Agency, Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan
ohtsu.takuyo@jaea.go.jp

Hisashi Takamizawa

Nuclear Safety Research Center, Japan Atomic Energy Agency, Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan
takamizawa.hisashi@jaea.go.jp

Yutaka Nishiyama

Nuclear Safety Research Center, Japan Atomic Energy Agency, Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan
nishiyama.yutaka93@jaea.go.jp

1Corresponding author.

ASME doi:10.1115/1.4040642 History: Received February 08, 2018; Revised June 14, 2018

Abstract

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) were 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 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.

Copyright (c) 2018 by ASME
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