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Journal Articles

New in-pile water loop facility for IASCC studies at JMTR

Tsukada, Takashi; Komori, Yoshihiro; Tsuji, Hirokazu; Nakajima, Hajime; Ito, Haruhiko

Proceedings of International Conference on Water Chemistry in Nuclear Reactor Systems 2002 (CD-ROM), 5 Pages, 2002/00

Irradiation assisted stress corrosion cracking (IASCC) is caused by the synergistic effects of neutron and gamma radiation, residual and applied stresses and high temperature water environment on the structural materials of vessel internals. IASCC has been studied since the beginning of the 1980s and the phenomenological knowledge on IASCC is accrued extensively. However, mainly due to the experimental difficulties, data for the mechanistic understanding and prediction of failures of the specific in-vessel components are still insufficient and further well-controlled experiments are needed [1]. In recent years, efforts to perform the in-pile materials test for IASCC study have been made at some research reactors [2-4]. At JAERI, a high temperature water loop facility was designed to install at the Japan Materials Testing Reactor (JMTR) to carry out the in-core IASCC testing. This report describes an overview of design and specification of the loop facility.

Journal Articles

Mechanical properties of austenitic stainless steels irradiated at 323K in the Japan materials testing reactor

Matsui, Yoshinori; Hoshiya, Taiji; Jitsukawa, Shiro; Tsukada, Takashi; Omi, Masao; ; Oyamada, Rokuro; *

Journal of Nuclear Materials, 233-237, p.188 - 191, 1996/00

 Times Cited Count:5 Percentile:46.08(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Evaluation of Low Temperature IGSCC of Type 304 Stainless Steel in In-Pile Water

; Kondo, Tatsuo

JAERI-M 83-063, 18 Pages, 1983/04

JAERI-M-83-063.pdf:1.53MB

no abstracts in English

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