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Nakano, Hiroko; Shibata, Hiroshi; Takeuchi, Tomoaki; Matsui, Yoshinori; Tsuchiya, Kunihiko
Proceedings of International Conference on Asia-Pacific Conference on Fracture and Strength 2016 (APCFS 2016) (USB Flash Drive), p.283 - 284, 2016/09
no abstracts in English
Hoshiya, Taiji*; Takaya, Shigeru*; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Nagae, Yuji*; Miwa, Yukio; Abe, Yasuhiro*; Omi, Masao; Tsukada, Takashi; Aoto, Kazumi*
Transactions of the Materials Research Society of Japan, 29(4), p.1687 - 1690, 2004/06
JAERI and JNC have begun the cooperative research of evaluation techniques of structural material degradation in FBR and LWR, which based on magnetic and corrosion properties along grain boundaries. Magnetic method has been proposed as the one of the non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. The effects of applied stress on natural magnetization were investigated on paramagnetic stainless steels having creep-damages. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steels in the vicinity of grain boundaries were estimated by AFM and Kerr effect microscope, respectively. These degradations were induced by changes in characteristics in the vicinity of grain boundaries. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear plants structural materials.
Nakano, Hiroko; Takeuchi, Tomoaki; Hirota, Noriaki; Tsuchiya, Kunihiko
no journal, ,
no abstracts in English
Nakano, Hiroko; Takeuchi, Tomoaki; Hirota, Noriaki; Ide, Hiroshi; Hanawa, Masashige*; Tsuchiya, Kunihiko
no journal, ,
Since the accident at the Fukushima Dai-ichi Nuclear Power Plants (NPPs), it has started a research and development which corresponds to the provisions to monitor NPPs situations during a severe accident (SA). Considering that reactor vessel might be exposed to high radiation at high temperature under SA, difficulties may arrear in the measurement of temperature and pressure in the reactor vessel for long time. Thus it is necessary for the measurements of them to develop mineral insulated (MI) cables with radiation- and heat-resistant. In this study, the electric and corrosion properties of the MI cables were evaluated in the conditions that may simulate SA to develop MI cables that can be used even in SA environment. Based on the experiments above, the prospect is obtained that MI cable using nickel alloy as a sheath material can be proposed as a high-temperature MI cable that can be used even in SA environment.