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Hanawa, Satoshi; Uchida, Shunsuke; Hata, Kuniki; Chimi, Yasuhiro; Kasahara, Shigeki*; Nishiyama, Yutaka
Proceedings of 20th Nuclear Plant Chemistry International Conference (NPC 2016) (USB Flash Drive), 10 Pages, 2016/10
The authors proposed and ECP evaluation model introducing irradiation-induced diffusion in the oxide layer to simulate neutron irradiation effect, and predicted with this model that ECP is started to depress from the neutron flux of about ten to the fourteenth per square meter. As the JMTR has in-pile loops applicable to water chemistry experiments, degree of irradiation effect on ECP appears in the in-pile loop was estimated by the model. Under oxygen injected condition, ECP in a capsule becomes constant along the vertical direction due to the presence of high amount of oxygen and hydrogen peroxide in a capsule. However, if neutron irradiation depress ECP, ECP in a capsule along vertical direction wouldn't become constant, and the degree to the decrement is detectable by experiments.
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.
; ; ; Watanabe, Hiroyuki; ;
JAERI-M 90-196, 45 Pages, 1990/11
no abstracts in English
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JAERI-M 86-068, 17 Pages, 1986/04
no abstracts in English
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JAERI-M 85-133, 137 Pages, 1985/09
no abstracts in English
; Kondo, Tatsuo
JAERI-M 83-063, 18 Pages, 1983/04
no abstracts in English
Yamamoto, Katsumune; Yokouchi, Iichiro; Okagawa, Seigo; ;
JAERI-M 83-007, 50 Pages, 1983/03
no abstracts in English
; Ikezoe, Yasumasa; Shimizu, Saburo; Nakajima, Hayato; ; ; ; ;
JAERI-M 82-081, 65 Pages, 1982/07
no abstracts in English
; Yamamoto, Katsumune; ; ; ; *
JAERI-M 9792, 27 Pages, 1981/11
no abstracts in English
Nihon Kagakkai-Shi, (6), p.1027 - 1033, 1981/00
no abstracts in English
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JAERI-M 9114, 185 Pages, 1980/10
no abstracts in English
; ;
JAERI-M 8184, 39 Pages, 1979/03
no abstracts in English
JAERI-M 7983, 18 Pages, 1978/11
no abstracts in English
JAERI-M 7982, 25 Pages, 1978/11
no abstracts in English
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JAERI-M 7459, 36 Pages, 1978/01
no abstracts in English
; ; Ikezoe, Yasumasa; Shimizu, Saburo; Nakajima, Hayato
JAERI-M 7246, 14 Pages, 1977/08
no abstracts in English
JAERI-M 7092, 27 Pages, 1977/05
no abstracts in English
; ; Ikezoe, Yasumasa; Shimizu, Saburo; Nakajima, Hayato
JAERI-M 6507, 11 Pages, 1976/03
no abstracts in English
Kitahara, Tanemichi; ; ; ; ; ; ;
Journal of Nuclear Science and Technology, 13(3), p.111 - 118, 1976/03
Times Cited Count：7no abstracts in English
; ; Kitahara, Tanemichi;
JAERI-M 6200, 22 Pages, 1975/08
no abstracts in English
