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Takahashi, Yoshikazu; Suwa, Tomone; Nabara, Yoshihiro; Ozeki, Hidemasa; Nunoya, Yoshihiko; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Takamura, Jun; Shibutani, Kazuyuki*; Chuheishi, Shinji; et al.
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The Japan Atomic Energy Agency (JAEA) is responsible for procuring all amounts of Central Solenoid (CS) Conductors for ITER, including CS jacket sections. The conductor is cable-in-conduit conductor (CICC) with a central spiral. A total of 576 Nb
Sn strands and 288 copper strands are cabled around the central spiral. The maximum operating current is 40 kA at magnetic field of 13 T. CS jacket section is circular in square type tube made of JK2LB, which is high manganese stainless steel with boron added. Unit length of jacket sections is 7 m and 6,300 sections will be manufactured and inspected. Outer/inner dimension and weight are 51.3/35.3 mm and around 90 kg, respectively. Eddy Current Test (ECT) and Phased Array Ultrasonic Test (PAUT) were developed for non-destructive examination. The defects on inner and outer surfaces can be detected by ECT. The defects inside jacket section can be detected by PAUT. These technology and the inspected results are reported in this paper.
Mizutani, Takumi; Hemmi, Tsutomu; Kajitani, Hideki; Matsui, Kunihiro; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo
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no abstracts in English
Yamane, Minoru; Koizumi, Norikiyo; Matsui, Kunihiro; Hemmi, Tsutomu; Kajitani, Hideki; Takano, Katsutoshi; Ando, Shinji
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no abstracts in English
Koizumi, Norikiyo; Nakahira, Masataka; Matsui, Kunihiro; Takano, Katsutoshi; Ando, Shinji; Yamane, Minoru; Iguchi, Masahide; Mizutani, Takumi
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no abstracts in English
Sn strands with deformation before heat treatmentSuwa, Tomone; Nabara, Yoshihiro; Nunoya, Yoshihiko; Takahashi, Yoshikazu; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Shibutani, Kazuyuki*; Murakami, Yukinobu*; Miyashita, Katsumi*; Sim, K.-H.*; et al.
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no abstracts in English
Tatsumoto, Hideki; Shirai, Yasuyuki*; Shiotsu, Masahiro*; Horie, Yuki*; Yoneda, Kazuya*; Matsuzawa, Takayuki*; Kobayashi, Hiroaki*; Naruo, Yoshihiro*; Inatani, Yoshifumi*
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no abstracts in English
Murakami, Haruyuki; Natsume, Kyohei; Kizu, Kaname; Tsuchiya, Katsuhiko; Koide, Yoshihiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Chikaraishi, Hirotaka*; et al.
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no abstracts in English
Kamiya, Koji; Furukawa, Masato; Onishi, Yoshihiro; Koide, Yoshihiko; Yoshida, Kiyoshi
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Upgrading JT-60 Tokamak to Superconducting Tokamak has been in progress as the Satellite Tokamak device (JT-60SA) in a collaborative project between EU and Japan. The JT-60SA will have the thermal shield at 80 K to reduce the heat load to the superconducting coils. The thermal shield consists of the vacuum vessel thermal shield (VVTS), the port thermal shield(PTS), and the cryostat thermal shield (CTS). A part of the VVTS and the PTS have already started manufacturing. The thermal shield is adjacent to the toroidal field coil, the design of the thermal shield shall take assembly process into account. In this report, design of the thermal shield, and current status of connecting couplers are reported.
Onishi, Yoshihiro; Kamiya, Koji; Kuramochi, Masaya; Yanagi, Shunki; Honda, Atsushi; Kizu, Kaname; Koide, Yoshihiko; Yoshida, Kiyoshi
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no abstracts in English