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Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Review 2014-030, 138 Pages, 2014/08
The prototype fast breeder reactor Monju has accumulated technical achievements in order to establish the fast breeder reactor cycle technology in Japan using the operation and maintenance experience, etc. This annual report summarizes the primary achievements and the data related to the plant management in Monju during fiscal 2013.
Miya, Naoyuki; *; Ushigusa, Kenkichi; Oikawa, Akira; Imai, Tsuyoshi; ; Nishitani, Takeo; Matsuzaki, Yoshimi; Kuriyama, Masaaki;
JAERI-M 92-140, 156 Pages, 1992/09
no abstracts in English
Tanigawa, Hisashi; Ueno, Kenichi; Inoue, Ryuichi; Takeda, Nobukazu; Kakudate, Satoshi
no journal, ,
The shield blanket in ITER has an active cooling structure necessitating hydraulic connections to the cooling water manifold. To maintain or replace the blanket, welding the hydraulic connection by remote handling is necessary. Access for the welding is limited in a small hole in the first wall because of spatial constraints related to neutron and heat fluxes. A bore welding tool is required. Laser and TIG welding tools have been developed, and the welding conditions have been optimized for all position welding to horizontally located pipes. Additionally capability of re-welding between as-cut and new pipes has been confirmed. Based on the results, applicability of laser and TIG welding are comparatively assessed.
Ishiguro, Takahiro; Hattori, Shushi*; Hattori, Tsukasa*; Shirahama, Takuma*; Ueda, Masashi
no journal, ,
In sodium cooled fast-reactors, opaque and highly chemical reactive sodium is used as coolant. Therefore, in the event of a loose part (dropped part) occurring, it is difficult to search and recover them under liquid sodium, potentially stopping the plant operation for a long time. The paper presents a prototype of the recovery mechanism, which is an important component of recover device for loose parts, and reports measurements and testing of it in liquid sodium.