(EXP3/12) MHD Characteristics in High-Beta Regime of the Large Helical Device
S. Sakakibara1), H. Yamada1),
K. Y. Watanabe1), Y. Narushima1),
K. Toi1), S. Ohdachi1), M. Takechi1),
S. Yamamoto3), K. Narihara1),
K. Tanaka1), N. Ashikawa2),
P. de Vries1), M. Emoto1), H. Funaba1),
M. Goto1), K. Ida1), H. Idei1),
K. Ikeda1), S. Inagaki1), N. Inoue1),
M. Isobe1), S. Kado1), O. Kaneko1),
K. Kawahata1), K. Khlopenkov1),
A. Komori1), S. Kubo1), R. Kumazawa1),
S. Masuzaki1), T. Minami1),
J. Miyazawa1), T. Morisaki1),
S. Morita1), S. Murakami1), S. Muto1),
T. Mutoh1), Y. Nagayama1),
Y. Nakamura1), H. Nakanishi1),
K. Nishimura1), N. Noda1), T. Notake3),
T. Kobuchi2), Y. Liang2), N. Ohyabu1),
Y. Oka1), M. Osakabe1), T. Ozaki1),
R. O. Pavlichenko1), B. J. Peterson1),
A. Sagara1), K. Saito3), R. Sakamoto1),
H. Sasao2), M. Sasao1), K. Sato1),
M. Sato1), T. Seki1), T. Shimozuma1),
M. Shoji1), H. Suzuki1), Y. Takeiri1),
N. Tamura2), T. Tokuzawa1), Y. Torii3),
K. Tsumori1), I. Yamada1),
S. Yamaguchi1), M. Yokoyama1),
Y. Yoshimura1), T. Watari1),
N. Nakajima1), K. Ichiguchi1),
H. Takahashi4), W. A. Cooper5),
K. Yamazaki1), O. Motojima1),
Y. Hamada1), M. Fujiwara1)
1) National Institute for Fusion Science, Toki, Japan
2) Department of Fusion Science, Graduate Univ. for Advanced Studies,
Hayama, Japan
3) Department of Energy Engineering and Science, Nagoya Univ.,
Nagoya, Japan
4) Princeton Plasma Physics Laboratory, Princeton University,
Princeton, USA
5) Centre de recherches en physique des plasmas, Ecole Polytechnique
Federale de Lausanne, Lausanne, Switzerland
Abstract. The highest volume averaged beta value of 2.2% at
Bt = 0.75 T (gas puff) and 2.4% at Bt = 1.3 T (pellet) in all of
helical devices have been achieved in the Large Helical Device (LHD). The
dependence of MHD activities has been investigated in NBI plasmas.
The n/m = 1/2 mode excited in the core region and = 1 resonant
modes in peripheral region have been observed. Both of the fluctuation
amplitudes increase with and the pressure gradient. The strong
n/m = 1/2 mode which affects plasma profile have been observed in
high- discharges and the abrupt disappearance of the mode leads to
the restoration of Te profile. Violent instabilities which terminate the
plasma and degradation of global energy confinement have not been observed
so far.
IAEA 2001