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Plasma and Fusion Research
Volume 7, 2402116 (2012)
Regular Articles
- Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8093, Japan
Abstract
TOKASTAR-2 is a small tokamak-helical hybrid device which can generate tokamak and helical configurations independently. In tokamak discharge experiment, the conductive shell was installed to increase plasma current by controlling the displacement of ohmically heated (OH) plasma. The suppression of the vertical displacement was demonstrated, but the OH plasma was still located slightly above the mid plane. To compensate this displacement, the balance between up and down vertical field coil currents should be adjusted. In addition, the construction of additional helical field coils is planned to form closed vacuum magnetic surfaces. The magnetic field line tracing analysis was carried out to determine the detailed shape and location of additional helical field coils. From the simulation, it was clarified that the location of magnetic surfaces and the averaged value of rotational transform can be controlled by adjusting coil current ratios.
Keywords
tokamak-helical hybrid, tokamak discharge, fast camera, helical coil, vacuum magnetic surface
Full Text
References
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This paper may be cited as follows:
Makoto HASEGAWA, Kozo YAMAZAKI, Hideki ARIMOTO, Tetsutarou OISHI, Reiya NISHIMURA and Tatsuo SHOJI, Plasma Fusion Res. 7, 2402116 (2012).