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Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Nakamichi, Masaru; Katsuyama, Kozo; Iwamatsu, Shigemi; Hasegawa, Teiji; Kodaka, Hideo; Takatsu, Hideyuki; et al.
JAEA-Technology 2009-007, 168 Pages, 2009/03
JAEA-Technology-2009-007.pdf:31.88MB
In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been being performed irradiation experiments of lithium titanate (Li
TiO
), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes (1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and (2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, datailed specifications and the installation methods were examined, based on results of a conceptual design and basic design. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility.
Sato, Kazuyoshi; Uehara, Masaharu*; Tamura, Kosaku*; Hashimoto, Masayoshi*; Ogino, Shunji*; Yagenji, Akira; Nagamatsu, Nobuhide*; Sekiya, Shigeki*; Takahashi, Hideo*; Motohashi, Keiichi*; et al.
JAEA-Technology 2006-024, 114 Pages, 2006/03
JAEA-Technology-2006-024.pdf:24.72MB
no abstracts in English
Sato, Kazuyoshi; Hashimoto, Masayoshi*; Nagamatsu, Nobuhide*; Yagenji, Akira; Sekiya, Shigeki*; Takahashi, Hideo*; Motohashi, Keiichi*; Ogino, Shunji*; Kataoka, Takahiro*; Ohashi, Hironori*; et al.
JAEA-Technology 2006-006, 587 Pages, 2006/03
JAEA-Technology-2006-006.pdf:46.04MB
no abstracts in English
Nakakura, Kensuke*; Yagenji, Akira*; Shoji, Teruaki*; Araki, Masanori; Neyatani, Yuzuru; Tanaka, Eiichi*; Shima, Hiroaki*
JAERI-Tech 2005-058, 61 Pages, 2005/09
JAERI-Tech-2005-058.pdf:4.49MB
The design of International Thermonuclear Experimental Reactor (ITER) had been done during the period of Engineering Design Activities (EDA) and its final deign report was published on July 2001. After that the further design studies have been performed as activities in the CTA and ITA periods. As for Tokamak complex, Japan Atomic Energy Research Institute (JAERI) performed preliminary study for both static and dynamic analyses with a few types of analysis models based on the Technical Guidelines for Aseismic Design of Nuclear Power Plants etc during EDA. In comparison with reactor building for nuclear fission power plant, its outside is not so different from reactor building's one. However, its structural characteristics inside building are apparently different from reactor building's one, because the bio shield of Tokamak complex has a lot of large penetration of ports. Therefore, characteristic of dynamic analysis models for Tokamak complex needs to be evaluated in order to perform the detailed design of Tokamak complex in account for site-dependent conditions. This report describes results of characteristic evaluation with representative analytical models for Tokamak complex, which are modeled with Finite Element Method and Lumped mass, and it is confirmed that adopted evaluation method of the bio shield wall and floor's stiffnesses around the bio shield wall for Lumped mass model is adequate.
Tsunematsu, Toshihide; Namba, Haruyuki*; Akutsu, Yoichi; Okawa, Yoshinao; Yagenji, Akira; Takeda, Masatoshi*; Yajima, Kensaku*; Nitta, Yoshio*; Kobayashi, Kenichi*; Maeda, Ikuo*; et al.
Fusion Engineering and Design, 41(1-4), p.415 - 420, 1998/09
Times Cited Count：4 Percentile：38.54(Nuclear Science & Technology)no abstracts in English
Okawa, Yoshinao; Yagenji, Akira; Wakui, Toshiaki*; Murano, Yoshihiro*; Kawakami, Kunio*; Yamakura, Hideki*
Heisei 10-Nendo (Dai-16-Kai) Denki Setsubi Gakkai Zenkoku Taikai Koen Rombunshu, p.175 - 176, 1998/00
no abstracts in English
