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Yoshida, Kiyoshi; Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji
no journal, ,
The upgrade of JT-60U magnet system to superconducting coils (JT-60SA) is carried out by both parties of Japan and EU in the framework of the Broader Approach agreement. In Japan, trail fabrication of superconducting conductors for the central solenoid (CS) and equilibrium field (EF) coils are progressed in short length (30m). The side of jackets is fixed by short length conductor sample. Detailed design of CS and EF coils are competed. the contract for CS and EF coil fabrication are started to design the manufacturing tools and to select an insulation material. The detailed design for thermal shield and helium distribution is progressed in Japan. In EU, the detailed design of the TF coils is competed. The assembly process to the tokamak is under studied to define geometric interface. The detailed design of the helium refrigerator and the high temperature current leads are progressed in EU.
Kamiya, Koji; Takenouchi, Tadashi; Ichige, Toshikatsu; Yoshida, Kiyoshi
no journal, ,
JT-60SA, which is planned to use superconducting magnets for plasma confinment, will use a thermal shield cooled at 80K as a radiation shield for 4K magnets. Therefore, the shape of the thermal shield strongly depends on the shape of the superconducting magnets. The specification and the shape of the toroidal field coil has been fixed this year, and 110 mm clearance between plasma vacuum vessel and the magnets has been acquired. In the present publication, the thermal shield has been designed in the 110 mm clearance and the thermal analysis has been conducted for a part of it.
Murakami, Haruyuki; Matsui, Kunihiro; Kizu, Kaname; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Okuno, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Imagawa, Shinsaku*; Mito, Toshiyuki*; et al.
no journal, ,
no abstracts in English
Komeda, Masao*; Kamiya, Koji; Honda, Atsushi; Takenouchi, Tadashi; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
Kajitani, Hideki*; Ueda, Hiroshi*; Ishiyama, Atsushi*; Murakami, Haruyuki; Koizumi, Norikiyo; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Matsui, Kunihiro; Hamada, Kazuya; Kawano, Katsumi; Koizumi, Norikiyo; Takahashi, Yoshikazu; Nakajima, Hideo; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Takahashi, Yoshikazu; Isono, Takaaki; Hamada, Kazuya; Nunoya, Yoshihiko; Nabara, Yoshihiro; Matsui, Kunihiro; Hemmi, Tsutomu; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki; et al.
no journal, ,
The toroidal field (TF) coil system of the International Thermonuclear Experimental Reactor (ITER) consists of 18 D-shape coils. The operating current, the maximum field and the stored magnetic energy are 68 kA, 11.8 T and about 41 GJ, respectively. Nb
Sn cable-in-conduit conductor (CICC) with a central channel is used. The superconducting cable consists of 900 NbSn strands and 522 copper strands, and they are cabled to a 5th stage cable with a central cooling spiral. The conductor manufacture started in 4 companies (strands in 2 companies, cabling, jacketing) in Japan, from March 2008. The 14.4 tonnes of strands were completed and satisfy their specifications in 2 companies. The copper dummy cable with a length of 760 m was successfully fabricated. The jacketing line was also completed. These details are reported.
Nakajima, Hideo; Chida, Yutaka; Takano, Katsutoshi; Tsutsumi, Fumiaki; Okuno, Kiyoshi; Niimi, Kenichiro*; Senda, Ikuo*
no journal, ,
no abstracts in English
Tatsumoto, Hideki; Shirai, Yasuyuki*; Shiotsu, Masahiro*; Kobayashi, Hiroaki*; Naruo, Yoshihiro*; Inatani, Yoshifumi*; Hata, Koichi*
no journal, ,
no abstracts in English