DC power system for superconducting coils of fusion plasma test facility LHD

被引:1
作者
National Institute for Fusion Science, Oroshi, 322-6, Tokishi, Gifu, 509-5292, Japan [1 ]
不详 [2 ]
不详 [3 ]
不详 [4 ]
不详 [5 ]
不详 [6 ]
不详 [7 ]
不详 [8 ]
不详 [9 ]
不详 [10 ]
不详 [11 ]
不详 [12 ]
不详 [13 ]
不详 [14 ]
机构
[1] National Institute for Fusion Science, Tokishi, Gifu, 509-5292, Oroshi
[2] Osaka University, Suitashi, Osaka
[3] Shinko Engineering and Maintenance Co., Ltd., Iwayakita, Nadaku, Kobeshi, Hyougo
[4] Aichi Electric Co., Ltd., Kasugaishi, Aichi, 486-8666, 1, Aichicho
[5] Department of Electrical Engineering, Faculty of Engineering, Osaka University
[6] Aichi Electric Co., Ltd.
来源
IEEJ Trans. Ind Appl. | 2006年 / 4卷 / 459-467+13期
关键词
Current control; Dc power supply; LHD; Magnetic coupling;
D O I
10.1541/ieejias.126.459
中图分类号
学科分类号
摘要
The Large Helical Device (LHD) is an experimental facility for fusion plasma using a large scale mutually coupled superconducting coil system and it is now operating at the National Institute for Fusion Science. This paper introduces the design and the operation results of the dc power systems to drive these coils. First, the outline of the LHD and the power supplies are described. Next, a control system and the current controller for the power supplies are introduced. Finally, some experimental results are introduced.
引用
收藏
页码:459 / 467+13
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