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Watanabe, Kazuhiro; Yamanaka, Haruhiko; Maejima, Tetsuya; Inoue, Takashi; Hanada, Masaya; Tanaka, Shigeru*; Kadowaki, Makoto*
no journal, ,
A DC -1 MV insulation transformer is required for ITER NBI power supply. However such insulation transformer has not been developed. Demonstration of the DC ultra high voltage insulation is essential to realize such insulation transformer. To demonstrate the insulation transformer, a transformer model has been designed and fabricated under the ITER research and development task. The high voltage test with the model has been successfully performed and it ensures that the real insulation transformer can be fabricated.
Watanabe, Kazuhiro; Yamanaka, Haruhiko; Yamaguchi, Kohei*; Kadowaki, Makoto*; Ichimura, Satoshi*
no journal, ,
An insulation transformer for ITER Project is required to supply AC power source for ion source and extractor power supplies located on DC -1 MV insulated deck. A mockup model for the insulation transformer has been developed to verify the insulation capability of DC -1 MV and assembling procedure. It has been successfully demonstrated for sufficient insulation of higher than DC -1 MV through dielectric tests.
Tobari, Hiroyuki; Hanada, Masaya; Watanabe, Kazuhiro; Kashiwagi, Mieko; Kojima, Atsushi; Dairaku, Masayuki; Seki, Norikatsu; Abe, Hiroyuki; Umeda, Naotaka; Yamanaka, Haruhiko; et al.
no journal, ,
Progress on technical development on ITER and JT-60SA neutral beam injector (NBI) were reported. In development of a 1 MV insulating transformer for ITER NB power supply, a bushing extracting 1 MV required a huge insulator that was impossible to manufacture. To solve this issue, a composite bushing with FRP tube and a small condenser bushing with insulation gas was newly developed. In development the HV bushing as an insulating feed through, voltage holding in large cylindrical electrodes inside the HV bushing was investigated. The scaling for vacuum insulation design of large cylindrical electrodes was obtained. Toward long pulse production and acceleration of negative ion beam, active control system of plasma grid temperature and a new extractor consisting of the extraction grid with high water cooling capability and aperture offset were developed. As a result, 15 negative ion beam has been achieved for 100 s. Also beam energy density has been increased two orders of magnitude.
