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Isono, Takaaki; Kawano, Katsumi; Nunoya, Yoshihiko; Takahashi, Yoshikazu; Okuno, Kiyoshi
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no abstracts in English
Sakurai, Takeru; Iguchi, Masahide; Nakahira, Masataka; Minemura, Toshiyuki*; Yanagi, Yutaka*; Osemochi, Koichi*
no journal, ,
no abstracts in English
Takahashi, Yoshikazu; Nabara, Yoshihiro; Nunoya, Yoshihiko; Suwa, Tomone; Tsutsumi, Fumiaki; Oshikiri, Masayuki; Ozeki, Hidemasa; Shibutani, Kazuyuki*; Kawano, Katsumi; Kawasaki, Tsutomu*; et al.
no journal, ,
Japan Atomic Energy Agency (JAEA) is procuring all amounts of NbSn conductors for Central Solenoid (CS) in the ITER project. Before start of mass-productions, the conductor should be tested to confirm superconducting performance in the SULTAN facility, Switzerland. The cable with a shorter twist pitch shows no degradation of Tcs against to electromagnetic load cycles. However, it is difficult to make the cable, because the diameter of the cable with shorter twist pitch is larger and the cable has to compact more. The technology for the cables with STP was developed in Japanese cabling suppliers. The several key technologies and production will be described in this paper.
Kawahara, Yuzuru*; Yamamoto, Yusuke*; Nakamura, Kazuya*; Takao, Tomoaki*; Yagai, Tsuyoshi*; Murakami, Haruyuki; Yoshida, Kiyoshi; Natsume, Kyohei*; Hamaguchi, Shinji*; Obana, Tetsuhiro*; et al.
no journal, ,
no abstracts in English
Nunoya, Yoshihiko; Takahashi, Yoshikazu; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Nabara, Yoshihiro; Takamura, Jun; Chuheishi, Shinji; Shibutani, Kazuyuki*; Suwa, Tomone; Matsuda, Hidemitsu*
no journal, ,
no abstracts in English
Nabara, Yoshihiro; Suwa, Tomone; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Sakurai, Takeru; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; et al.
no journal, ,
no abstracts in English
Matsui, Kunihiro; Yamane, Minoru; Hemmi, Tsutomu; Kajitani, Hideki; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo
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no abstracts in English
Yamane, Minoru; Matsui, Kunihiro; Kajitani, Hideki; Hemmi, Tsutomu; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo
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no abstracts in English
Takano, Katsutoshi; Ando, Shinji; Matsui, Kunihiro; Koizumi, Norikiyo
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no abstracts in English
Hemmi, Tsutomu; Yamane, Minoru; Kajitani, Hideki; Matsui, Kunihiro; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo
no journal, ,
no abstracts in English
Kajitani, Hideki; Hemmi, Tsutomu; Matsui, Kunihiro; Yamane, Minoru; Koizumi, Norikiyo; Obana, Tetsuhiro*; Hamaguchi, Shinji*; Takata, Suguru*; Chikaraishi, Hirotaka*; Natsume, Kyohei*; et al.
no journal, ,
Two double pancake coils of ITER TF coil are electrically connected at the joint. To evaluate the ITER TF joint performance, the joint test sample, which consists of two TF conductors and has full size joint part, was fabricated. The joint sample was tested using NIFS test facility under the condition of current of 68kA and external field of 2T. As a result, the joint resistance could be 1nohm, which is sufficiently small. In this presentation, detail of the test result is reported.
Saura, Keisuke*; Obana, Tetsuhiro*; Takata, Suguru*; Natsume, Kyohei*; Hamaguchi, Shinji*; Chikaraishi, Hirotaka*; Takahata, Kazuya*; Imagawa, Shinsaku*; Kajitani, Hideki; Hemmi, Tsutomu; et al.
no journal, ,
The full size joint test of ITER TF coil was performed using NIFS test facility. Because of transport current of 68kA, which is high current never experienced before, the reduction of cupper busbar heating was needed. Therefore, high temperature superconducting (HTS) busbar (Bi2212 fabricated by Sumitomo Electric Co.,Ltd) was installed in parallel with cupper busbar. In the test, current of HIS busbar was measured using rogowski coil and it was observed that the current of 20 kA could be distributed to HTS busbar. Therefore, the cupper busbar heating could be reducted to about 60% compared with the case of no HTS busbar.
Koizumi, Norikiyo; Nakahira, Masataka; Matsui, Kunihiro; Hemmi, Tsutomu; Kajitani, Hideki; Sakurai, Takeru; Takano, Katsutoshi; Yamane, Minoru; Ando, Shinji
no journal, ,
no abstracts in English
Kamiya, Koji; Onishi, Yoshihiro; Furukawa, Masato; Yoshida, Kiyoshi
no journal, ,
JT-60SA thermal shields consists of 3 main components; vacum vessel thermal shield, port thermal shield, and cryostat thermal shield. Those components further consists of multiple panels with a gap of 60 mm, which are mutually connected by couplers. In order to shield the radiation from the cryostat and from the plasma vacuum vessel, JT-60SA plans to cover the 60 mm gaps with stainless steel film (radiation cover). In this study, mechanical test results of electrically insulated cover will be reported. In the JT-60SA, gravity supports of toroidal field coils (TFC) will have the thermal anchor at the middle of the support from CTS. Since TFC and TS needs to be electrically insulated, the thermal anchors are electrically insulated. In this study, heat transfer test of the thermal anchor will be reported.
Yoshida, Kiyoshi; Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Koide, Yoshihiko
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no abstracts in English
Murakami, Haruyuki; Kizu, Kaname; Kamiya, Koji; Tsuchiya, Katsuhiko; Koide, Yoshihiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Chikaraishi, Hirotaka*; et al.
no journal, ,
no abstracts in English