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; ; Konno, Chikara; Maekawa, Fujio; Maekawa, Hiroshi; ; ;
Fusion Engineering and Design, 28, p.525 - 533, 1995/00
no abstracts in English
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.
Tobari, Hiroyuki; Hanada, Masaya; Watanabe, Kazuhiro; Kashiwagi, Mieko; Dairaku, Masayuki; Yamanaka, Haruhiko; Maejima, Tetsuya; Umeda, Naotaka; Abe, Hiroyuki; Terunuma, Yuto; et al.
no journal, ,
JAEA has started procurement activities for ITER NB test facility (NBTF). NBTF being under construction in Padova, Italy has an objective to establish beam technology for 1 MeV, 40 A D- beam prior to ITER operation. JAEA procures high voltage components of 1 MV power supply such as insulating transformer and HV bushing as insulating feedthrough. Requirements to realize those components exceeds existing technology level, hence JAEA has pushed R&D. As for 1 MV insulating transformer, insulating method with double-walled insulator was newly developed. As for the HV bushing, a new forming method of the world largest ceramic ring and brazing technique were developed, and then a technology that meets ITER requirement has been confirmed. Procurement activities have been started from 2012 and now is undergoing as scheduled. Manufacturing of components will be completed by 2015 and those will be transported and installed in Padova in 2016. Commissioning will start in 2017.
Dairaku, Masayuki; Tobari, Hiroyuki; Abe, Hiroyuki; Seki, Norikatsu; Hanada, Masaya; Watanabe, Kazuhiro; Kashiwagi, Mieko; Yamanaka, Haruhiko; Umeda, Naotaka
no journal, ,
no abstracts in English
Tobari, Hiroyuki; Dairaku, Masayuki; Kojima, Atsushi; Umeda, Naotaka; Abe, Hiroyuki; Seki, Norikatsu; Shibata, Naoki; Kashiwagi, Mieko; Watanabe, Kazuhiro; Hanada, Masaya
no journal, ,
JAEA procures the HV bushing for NBTF, which is under construction in Padova, Italy. To insulate rated voltage of 1 MV, large-area, five-layered electrostatic screens are installed in the limited space inside the HV bushing. However voltage holding characteristics of such large-area, multi-layer electrode is not clarified, and this characteristics is investigated with mockup electrode scalable to the HV bushing. Then, the HV bushing has been designed with voltage holding characteristics derived from the mockup experiment. Assembly of the HV bushing has been finished by September, 2015. Now, voltage holding test of the manufactured HV bushing is on-going, and voltage holding capability up to 240 kV for each of electrostatic screen layer. After confirmation for 1 MV insulation, the HV bushing will be shipped to NBTF site.
