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Kamiya, Koji; Onishi, Yoshihiro; Ichige, Toshikatsu; Murakami, Haruyuki; Yoshida, Kiyoshi; Mizumaki, Shoichi*
no journal, ,
JT-60SA, which replaces all the coils for plasma confinement with superconducting coils, installs a 80 K radiation shield, so called the thermal shield, between the plasma vacuum vessel at 323 K and the superconducting coils at 4 K. In the presentation, structure analysis and estimation of the force loads to connection devices which connect the thermal shield panels are reported. In addition, trial manufacturing of 10 degree outer vacuum vessel thermal shield (VVTS), and connection test with existing trial manufacturing of an inner VVTS are also reported.
Kizu, Kaname; Tsuchiya, Katsuhiko; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Ichige, Toshikatsu; Asakawa, Shuji; Yoshida, Kiyoshi
no journal, ,
Superconducting cables and jackets delivered from manufacturer are fabricated into superconductor at jacketing facility in Japan Atomic Energy Agency. Then, conductors are supplied to coil manufacturer. Fabrication of conductors for equilibrium field coils were started from 2010. 26 conductors were fabricated up to 9 September 2011. 22 conductors at storage building were loosened by Great East Japan Earthquake. Conductors were repaired. It was confirmed that conductors can be used for coil. On the other hand, fabrication of conductors for central solenoid was started from July 2011. 4 conductors were fabricated.
Hamada, Kazuya; Nunoya, Yoshihiko; Takahashi, Yoshikazu; Isono, Takaaki; Nabara, Yoshihiro; Hemmi, Tsutomu; Matsui, Kunihiro; Kawano, Katsumi; Ebisawa, Noboru; Oshikiri, Masayuki; et al.
no journal, ,
The ITER Central Solenoid (CS) conductor is composed of 576 Nb
Sn superconducting strands and 288 Cu strands assembled together into a multistage cable and protected by a circle-in-square jacket with the outer dimension of 49 mm 
49 mm. In R&D to prepare for the ITER CS conductor manufacturing, full size conductor performance test and jacket welding test and mechanical tests have been performed. In the presentation, the R&D activities are presented, showing that as a result of this R&D, the CS conductor manufacturing technologies have been confirmed to start the procurement of the CS conductor.
Murakami, Haruyuki; Kizu, Kaname; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Imagawa, Shinsaku*; Mito, Toshiyuki*
no journal, ,
no abstracts in English
Kajitani, Hideki; Murakami, Haruyuki; Hemmi, Tsutomu; Koizumi, Norikiyo; Nakajima, Hideo
no journal, ,
The critical current of a cable-in-conduit conductor (CICC) for an ITER TF and CS coil has been measured using the SULTAN test facility. However, it was found that the measured critical current was lower than that evaluated from the critical current performance of a single strand. One of the explanations for this phenomenon is (1) a bending to strand generated by electromagnetic force and (2) a local degradation of strand due to the feature of SULTAN test facility. In this study, we mainly (1) established the model to simulate the bending to strand due to electromagnetic force. Using this model, we calculated a current distribution in the conductor and studied the degradation of conductor performance. As the result, the current distribution was almost uniform and non-uniform voltage distribution as in the tests did not occur. It means that mainly a (2) local degradation may generate non-uniform voltage distribution. We will also study this influence in the near the future.
Tatsumoto, Hideki; Shirai, Yasuyuki*; Shiotsu, Masahiro*; Naruo, Yoshihiro*; Kobayashi, Hiroaki*; Inatani, Yoshifumi*
no journal, ,
no abstracts in English