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Optimization of Tokamak Plasma Equilibrium Control in TOKASTAR-2

Reiya NISHIMURA, Hideki ARIMOTO, Takaaki FUJITA, Tomohiro UEDA, Tatsuya SAKITO and Kozo YAMAZAKI¹⁾

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

1)

Nagoya University Professor Emeritus

(Received 9 December 2013 / Accepted 10 March 2014 / Published 7 May 2014)

Abstract

To improve capability of tokamak plasma equilibrium control in TOKASTAR-2, a pair of pulsed vertical field coils (PVF coils) was installed in 2012. Optimization of PVF coil current waveform was made with re-calculation using TOSCA code in varying the conditions of tokamak discharge. Then, simulation of the electric circuit of PVF coil system with LTspice code was done to find the optimum capacitance and charging voltage of capacitor for PVF coils consistent to the optimal current waveform. Eventually capacitor parameters for PVF coils to be used as base for experiment were obtained.

Copyright (c) 2014 The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

TOKASTAR-2, tokamak, stellarator, hybrid configuration, TOSCA code, eddy current

DOI: 10.1585/pfr.9.3402059

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References

• [1] T. Oishi, K. Yamazaki, K. Okano, H. Arimoto, K. Baba, M. Hasegawa and T. Shoji, J. Plasma Fusion Res. SERIES 9, 69 (2010).
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This paper may be cited as follows:

Reiya NISHIMURA, Hideki ARIMOTO, Takaaki FUJITA, Tomohiro UEDA, Tatsuya SAKITO and Kozo YAMAZAKI, Plasma Fusion Res. 9, 3402059 (2014).