T. Watari , T. Shimozuma , Y. Takeiri ,
R. Kumazawa , T. Mutoh , M. Sato , O. Kaneko ,
K. Ohkubo , S. Kubo , H. Idei , Y. Oka , M. Osakabe ,
T. Seki , K. Tsumori , Y. Yoshimura , R. Akiyama ,
T. Kawamoto , S. Kobayashi , F. Shimpo , Y. Takita ,
E. Asano , S. Itoh , G. Nomura , T. Ido , M. Hamabe ,
M. Fujiwara , A. Iiyoshi , S. Morimoto 1,
T. Bigelow 2, Y. P. Zhao 3, X. D. Li 4
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki,
509-5292 Japan
1 Kanazawa Institute of Technology, 7-1, Oogigaoka, Nonoichi,
Ishikawa, 921, Japan
2 Oak Ridge National Laboratory, TN37831, USA.
3 Institute of Plasma Physics, Academia Sinica, 230031, Hefei,
Anhui, China
4 Southwestern Institute of Physics, Chengdu, 610041, China
Abstract
Construction of the LHD
has been completed and it went into the experimental phase in early April
1998. The first plasma was obtained with ECH with a power level of 300
kW. Three heating schemes, ECH, ICRF, and NBI, are adopted and join the
heating experiment in the second experimental campaign. Since the LHD has
superconducting coils, one of the missions of plasma heating in the LHD is
demonstration of a steady state plasma. Intensive technology development for
steady state plasma heating has been carried out at NIFS since 1992. The paper
summarizes the achievements of these developmental activities in the past
several years. The knowledge obtained may be applicable to ITER , where steady
state plasma heating is essential.
IAEA 1999