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Okuno, Kiyoshi; Takahashi, Yoshikazu; Koizumi, Norikiyo; Nakajima, Hideo
Heisei-23-Nen Denki Gakkai Zenkoku Taikai Koen Rombunshu, 5, p.S1(34) - S1(37), 2011/03
When we talk about the history and future perspective of superconducting technology, we recognize its important relation to fusion research. Magnetic confinement fusion devices, represented by a tokamak and helical systems, promoted the scale-up in size, high field and high performances of superconducting magnets, together with the production of superconductors at industry level. ITER will play this role in the first quarter of the 21st century. The construction of ITER has already started in Cadarache, France, with a milestone to obtain the 1st plasma in November 2019. The ITER participants have started their procurement activities for superconducting magnets to achieve this milestone. This is being performed with the highest superconducting technology at present and will bring a major progress in this area when completed.
Oda, Yasuhisa; Kajiwara, Ken; Takahashi, Koji; Sakamoto, Keishi
no journal, ,
no abstracts in English
Koizumi, Norikiyo; Matsui, Kunihiro; Hemmi, Tsutomu; Takano, Katsutoshi; Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo
no journal, ,
no abstracts in English
Sasaki, Akira; Torii, Tatsuo; Takahashi, Eiichi*; Kato, Susumu*; Kishimoto, Yasuaki*; Kanazawa, Seiji*; Fujii, Takashi*
no journal, ,
no abstracts in English
Tsuchida, Kazuki; Watanabe, Kazuhiro; Yamanaka, Haruhiko; Takemoto, Jumpei; Inoue, Takashi; Tanaka, Shigeru*; Yamashita, Yasuo*
no journal, ,
In ITER Neutral Beam (NB) injection system, the negative ion source and the accelerator should be cooled to generate high energy and high power beam for the prolonged operation. Those devices will be settled at high electric potential of -1 MV and an water choke is needed in the cooling water line to insulate the high voltage. The water choke for ITER should meet the following specifications; high water pressure (2 MPa) and high leak current (several ten mA) due to the reduction of resistivity in hot water (65 
C), etc. So, we developed a ceramic insulation tube for the water choke of ITER NB system and it's performance was confirmed by mechanical and withstand voltage tests. From the test results, it was confirmed the developed ceramic tube has sufficient performance (
110 kV/tube) as a part of ITER water choke. The anti-corrosion and anti-dissolution of the sealing materials in the ceramic tube was also confirmed under the high leak current condition.
Watanabe, Kazuhiro; Umeda, Naotaka; Kashiwagi, Mieko; Dairaku, Masayuki; Takemoto, Jumpei; Taniguchi, Masaki; Tsuchida, Kazuki; Tobari, Hiroyuki; Yamanaka, Haruhiko; Inoue, Takashi; et al.
no journal, ,
In the ITER project, negative-ion-based neutral beam injectors (NBI) which can inject deuterium neutral beams of 1 MeV, 16.5 MW per one injector are planned. The authors will report the subjects of the system and present status of the development for the major components of Japanese procurements for the ITER NBI and the ITER NBI test facility.