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Author(s):
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, T. Bigelow and Y.P. Zhao
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Title:
Steady State Heating Technology Development for LHD
Date of publication:
Oct. 1998
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Key words:
IAEA, fusion energy conference, Yokohama
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Abstract:
The LHD has finished construction and went into Experimental phase in early April 1998. The first plasma was obtained with ECH with the power level of 300kW. Three heating schemes, ECH, ICRF, and NBI are adopted and join the heating experiment in the second experimental campaign. Since the l.HD has super-conducting coils, one of' the missions of plasma heating in LHD is demonstration of steady state plasma. Intensive technology development for steady state plasma heating has been carried out at NIFS since 1992. This paper summarizes the achievement of these developmental activities in the past several years. The knowledge obtained may be applicable to ITER, where steady state plasma heating is essential.
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