Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
6744395 | Fusion Engineering and Design | 2017 | 4 Pages |
Abstract
Toward the 1 MV power supply system for the ITER neutral beam injector consisting of various components with oil insulation, gas insulation and vacuum insulation, design and manufacturing of dc ultra-high-voltage component have been progressed. Thermal design of long transmission line up to 100 m was established. In order to design the high-temperature water channel for the plasma grid at 1 MV potential, the resistivity of high-purity water at 180 °C was measured for the first time. With the obtained resistivity, realistic high-temperature water circulating system was designed. A high-voltage bushing to transmit multiple voltages simultaneously has been also developed through a careful experimental study on vacuum insulation characteristics with multi-gaps coaxial electrodes. With the empirical scaling the electrostatic screen was designed taking into account effect of multi-gap and expected deformation such as thermal elongation during operation. After the assembly, stable voltage holding of 240 kV at each stage was confirmed in the manufactured HV bushing.
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Hiroyuki Tobari, Mieko Kashiwagi, Kazuhiro Watanabe, Tetsuya Maejima, Atsushi Kojima, Naotaka Umeda, Masayuki Dairaku, Yuki Oda, Haruhiko Yamanaka,