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Journal Articles

Effects of hydrogen peroxide and oxygen on polarization curves of stainless steel in high temperature pure water

Sato, Tomonori; Uchida, Shunsuke; Tsukada, Takashi; Morishima, Yusuke*; Miyazawa, Takahiro*; Sato, Yoshiyuki*

Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems 2006 (CD-ROM), 6 Pages, 2006/10

To evaluate ECP response of stainless steel in H$$_{2}$$O$$_{2}$$ condition, the polarization of stainless steel in highly purified water at elevated temperature was measured. In this study a temporary Pt reference electrode, which was fixed at a natural potential vs. the Ag/AgCl reference electrode, was applied for polarization measurements. Stepwise voltage was supplied to a working electrode vs. the temporary reference electrode. As a result, the followings were concluded. (1) It was confirmed that both anodic and cathodic current densities increased as [H$$_{2}$$O$$_{2}$$] increased from 10 ppb to 100 ppb. It might be caused by the contribution of anodic reaction of H$$_{2}$$O$$_{2}$$ as well as cathodic reaction of H$$_{2}$$O$$_{2}$$. (2) Neither anodic nor cathodic polarization curves change as [O$$_{2}$$] increase from 200 ppb to 2400 ppb. It might be caused by the mitigation of iron dissolution and cathodic reaction of O$$_{2}$$ by the formation of protective oxide layer and lower oxide dissolution.

Journal Articles

Properties of oxide films on stainless steel exposed to hydrogen peroxide and oxygen in high temperature water

Uchida, Shunsuke; Sato, Tomonori; Tsukada, Takashi; Sato, Yoshiyuki*; Miyazawa, Takahiro*; Terachi, Takumi*; Wada, Yoichi*; Hosokawa, Hideyuki*

Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems 2006 (CD-ROM), 6 Pages, 2006/10

no abstracts in English

Journal Articles

Results of in-pile SCC growth tests in high temperature water at JMTR

Tsukada, Takashi; Kaji, Yoshiyuki; Ugachi, Hirokazu; Nagata, Nobuaki*; Dozaki, Koji*; Takiguchi, Hideki*

Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems 2006 (CD-ROM), 5 Pages, 2006/10

Irradiation assisted stress corrosion cracking (IASCC) has been recognized as the aging issue of core-internal materials of the light water reactors (LWRs). The synergistic effect of neutron/$$gamma$$ radiation, stress and high temperature water on the materials in the reactor core is significant to understand IASCC behavior. Therefore, the in-pile IASCC testing is one of the key experiments to investigate IASCC mechanism, and also to assess the reliability of the PIE data. A high temperature water loop facility was installed at the Japan Materials Testing Reactor (JMTR) to carry out the in-pile IASCC testing. Using the loop facility, in-pile IASCC growth tests have been successfully carried out in the irradiation capsule under simulated BWR condition. The results showed that the effect of synergy of neutron/$$gamma$$ radiation and stress/water environment on SCC growth rate was considered to be small within the present test conditions.

Journal Articles

In-core ECP sensor designed for the IASCC experiments at JMTR

Tsukada, Takashi; Miwa, Yukio; Ugachi, Hirokazu; Matsui, Yoshinori; Itabashi, Yukio; Nagata, Nobuaki*; Dozaki, Koji*

Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems (CD-ROM), 5 Pages, 2004/10

IASCC initiation and propagation tests will be performed on the per-irradiated specimen in the Japan Materials Testing Reactor (JMTR). Since in core, the radiolysis of water causes a generation of various kind of radical species and some oxidizing species such as hydrogen peroxide, the water chemistry in irradiation capsules must be assessed by measurements of the electrochemical corrosion potential (ECP). For the in-core measurement of ECP in JMTR, we fabricated and tested the Fe/Fe$$_{3}$$O$$_{4}$$ type ECP sensor. After the fabrication, the function of each sensor was examined in high temperature water by out-of-core thermal cycling and high temperature holding tests.

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.

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