Plasma and Fusion Research
Volume 3, S1058 (2008)
Regular Articles
- Graduate School of Energy Science, Kyoto University, Gokasho, Uji, Kyoto 611-0011, Japan
- 1)
- National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292, Japan
- 2)
- Graduate School of Engineering, Kyoto University, Yoshida, Kyoto, Kyoto 606-8501, Japan
Abstract
Numerical analysis is performed for a low beta neutral beam heated plasma and a superdense core plasma in the Large Helical Device (LHD) to investigate the time evolution of the rotational transform profile, which is calculated consistently with the three-dimensional magnetohydrodynamics equilibrium. Although there is a considerable amount of noninductive current flow, such as the bootstrap and Ohkawa currents, the inductive current component prevents a rapid change of the rotational transform profile in these plasmas.
Keywords
stellarator/heliotron, Large Helical Device, net plasma current, rotational transform, bootstrap current, Ohkawa current, inductive current
Full Text
References
- [1] Yuji Nakamura et al., Fusion Sci. Technol. 50, 457 (2006).
- [2] M. Sato et al., submitted to Plasma Fusion Res.
- [3] Yuji Nakamura et al., Proc. of 21th IAEA Fusion Energy Conf. (Chengdu, China, 2006) IAEA-CN-149/TH/P7-1.
- [4] S.P. Hirshman and D.J. Sigmar, Nucl. Fusion 21, 1079 (1981).
- [5] S.P. Hirshman, W.I. van Rij and P. Merkel, Comput. Phys. Commun. 43, 143 (1986).
- [6] P.I. Strand and W.A. Houlberg, Phys. Plasma 8, 2782 (2005).
- [7] K.Y. Watanabe et al., J. Plasma Fusion Res. Ser. 5, 124 (2002).
- [8] T. Morisaki et al., Phys. Plasma 14, 056113 (2007).
This paper may be cited as follows:
Yuji NAKAMURA, Kiyomasa WATANABE, Yoshiro NARUSHIMA, Katsumi IDA, Mikiro YOSHINUMA, Satoru SAKAKIBARA, Hisamichi FUNABA, Kazuo KAWAHATA, Masayuki YOKOYAMA, Noriyoshi NAKAJIMA and Atsushi FUKUYAMA, Plasma Fusion Res. 3, S1058 (2008).