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Journal Articles

Study of irradiation effect on ECP using in-pile loops in the JMTR

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.

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.

JAEA Reports

In-pile loop OWL-2 and irradiation tests done with it

; ; ; Watanabe, Hiroyuki; ;

JAERI-M 90-196, 45 Pages, 1990/11

JAERI-M-90-196.pdf:1.67MB

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

JAEA Reports

Measurements of Fission Products Released in Primary Cooling System of OWL-1 Loop

Yamamoto, Katsumune; Yokouchi, Iichiro; Okagawa, Seigo; ;

JAERI-M 83-007, 50 Pages, 1983/03

JAERI-M-83-007.pdf:1.65MB

no abstracts in English

JAEA Reports

Data Sheets of Fission Product Release Experiments for Light Water Reactor Fuel (III)

; Yamamoto, Katsumune; ; ; ; *

JAERI-M 9792, 27 Pages, 1981/11

JAERI-M-9792.pdf:2.18MB

no abstracts in English

Journal Articles

Studies of ceramic fuels with use of fission gas release loop, 4; Fission gas release from uranium carbide in the presence of trace amounts of water vapor

; ; ; Shiba, Koreyuki; ; ; ;

Journal of Nuclear Science and Technology, 11(9), p.387 - 394, 1974/09

 Times Cited Count:2

no abstracts in English

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