Experiments of tokamak discharge and simulation of magnetic field configuration in tokamak-helical hybrid device tokastar-2

被引：1

作者：

Hasegawa, Makoto ^{[1
]}

Yamazaki, Kozo ^{[1
]}

Arimoto, Hideki ^{[1
]}

Oishi, Tetsutarou ^{[1
]}

Nishimura, Reiya ^{[1
]}

Shoji, Tatsuo ^{[1
]}

机构：

[1] Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8093, Japan

来源：

Plasma and Fusion Research | 2012年 / 7卷 / SPL.ISS.1期

关键词：

Magnetic fields - Electric discharges - Tokamak devices;

D O I：

10.1585/pfr.7.2402116

中图分类号：

学科分类号：

摘要：

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. © 2012 The Japan Society of Plasma Science and Nuclear Fusion Research.

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