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Chida, Yutaka; Takano, Katsutoshi; Nakajima, Hideo; Osemochi, Koichi*; Niimi, Kenichiro*; Tokai, Daisuke*
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Matsui, Kunihiro; Koizumi, Norikiyo; Hemmi, Tsutomu; Takano, Katsutoshi; Chida, Yutaka; Shimizu, Tatsuya; Nakajima, Hideo
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Hemmi, Tsutomu; Harjo, S.; Matsui, Kunihiro; Nunoya, Yoshihiko; Koizumi, Norikiyo; Nakajima, Hideo; Ito, Takayoshi; Aizawa, Kazuya; Suzuki, Hiroshi; Machiya, Shutaro*; et al.
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Residual strain in conductors is caused by the difference in the coefficient of expansion between strands and the jacket over a temperature range of 5 - 923 K. The properties of strands vary significantly, depending on the residual strain. It is important to clarify the residual strain as part of the evaluation of performance. However, the residual strain of strands in the conductor has not been measured so far because of their complicated configuration and their location in a jacket. The engineering materials diffractometer "Takumi" in J-PARC can measure residual strain using neutron diffraction. In this study, neutron diffraction using the Takumi was applied to the measurement of residual strain in strands for the ITER TF conductor. Results indicate that the residual strain of strands in the conductor can be determined, thereby clarifying the mechanism of residual strain and its relationship to performance.
Takano, Katsutoshi; Koizumi, Norikiyo; Tsutsumi, Fumiaki; Nakajima, Hideo; Hatanaka, Hideo*; Uno, Tsuyoshi*; Natsume, Yoshihisa*
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Sn superconducting strand for ITER TF coilNabara, Yoshihiro; Isono, Takaaki; Nunoya, Yoshihiko; Koizumi, Norikiyo; Hamada, Kazuya; Matsui, Kunihiro; Hemmi, Tsutomu; Oshikiri, Masayuki; Uno, Yasuhiro*; Seki, Shuichi*; et al.
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Hamada, Kazuya; Takahashi, Yoshikazu; Isono, Takaaki; Nunoya, Yoshihiko; Matsui, Kunihiro; Nabara, Yoshihiro; Hemmi, Tsutomu; Kawano, Katsumi; Yoshikawa, Masatoshi*; Oshikiri, Masayuki; et al.
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Japan Atomic Energy Agency is in charge of procurement of Toroidal Field (TF) coil and conductors for International Thermonuclear Experimental Reactor(ITER) as a domestic agency of ITER in Japan. The TF conductor is composed of cable using 900 superconducting strands and 522 copper strands with a diameter of 0.8mm sheathed in the jacket with a thickness of 2mm and outer diameter of 43.7mm and the maximum length is 760m. The procurement of conductor was started from 2008 and preparations of strands, cabling, jacket and jacketing facility have progressed under the cooperation from industries. As a result, preparation to manufacture conductor is completed. First of all, to demonstrate the manufacturing procedure, 760m long dummy conductor has been manufactured and successfully completed. Based on the achievement, Japan started to make superconducting conductor. In the conference, status of procurement of TF conductor and conductor manufacturing technologies are introduced.
Al CIC conductorKoizumi, Norikiyo; Matsui, Kunihiro; Nakajima, Hideo; Takeuchi, Takao*; Banno, Nobuya*
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Asakawa, Shuji; Yoshida, Kiyoshi
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Kamiya, Koji; Ichige, Toshikatsu; Yoshida, Kiyoshi
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JT-60SA, which plans to replace all coils for the plasma confinement with superconductor, needs to enclose the superconducting coils with the thermal shield in order to reduce the radiation heat load from the ambient temperature. The thermal shield on the plasma vacuum vessel side (VVTS) requires the manufacturing and assembly torelance with high accuracy due to the narrow space between the toroidal field coil and the VVTS. Therefore, it is important to determine the manufacturing torelance from the trial manufacturing for the VVTS design. In this talk, the results including the VVTS manufacturing torelance determined from the trial manufacturing are presented.
Kizu, Kaname; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Imagawa, Shinsaku*; et al.
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In JT-60SA, magnets system consists of 18 toroidal field (TF) coils, 4 stacks of central solenoid (CS) and 6 plasma equilibrium field (EF) coils. The CS and EF coils are procured by Japan. The maximum magnetic field and maximum current of EF coils is 6.2 T, 20 kA. EF coil conductors are NbTi cable-in-conduit (CIC) conductor. Delivered superconducting cables and jackets are fabricated into CIC conductors at the jacketing facility with the length of 680 m constructed in the Naka site of JAEA. The production of superconductors with 444 m in length for actual EF coils was started from March 2010. The measurements of superconducting performance like current sharing temperature were conducted prior to the mass production. The production and test results of EF conductors will be described.
Murakami, Haruyuki; Ichige, Toshikatsu; Kizu, Kaname; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Imagawa, Shinsaku*; et al.
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Komeda, Masao*; Kamiya, Koji; Honda, Atsushi; Takenouchi, Tadashi*; Yoshida, Kiyoshi
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no abstracts in English