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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
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
O 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 [HO] increased from 10 ppb to 100 ppb. It might be caused by the contribution of anodic reaction of HO as well as cathodic reaction of HO. (2) Neither anodic nor cathodic polarization curves change as [O] increase from 200 ppb to 2400 ppb. It might be caused by the mitigation of iron dissolution and cathodic reaction of O by the formation of protective oxide layer and lower oxide dissolution.
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/
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/ radiation and stress/water environment on SCC growth rate was considered to be small within the present test conditions.