Experimental studies on NBI and ICRF heated plasmas in the large helical device

K. Kawahata, N. Ohyabu, O. Kaneko, A. Komori, H. Yamada, N. Ashikawa, P. De Vries, M. Emoto, H. Funaba, M. Goto, K. Ida, H. Idei, K. Ikeda, S. Inagaki, N. Inoue, M. Isobe, S. Kado, K. Khlopenkov, S. Kubo, R. KumazawaS. Masuzaki, T. Minami, J. Miyazawa, T. Morisaki, S. Morita, S. Murakami, S. Muto, T. Mutoh, Y. Nagayama, Y. Nakamura, H. Nakanishi, K. Narihara, K. Nishimura, N. Noda, T. Notake, T. Kobuchi, Y. Liang, S. Ohdachi, Y. Oka, M. Osakabe, T. Ozaki, R. O. Pavlichenko, B. J. Peterson, A. Sagara, K. Saito, S. Sakakibara, R. Sakamoto, H. Sasao, M. Sasao, K. Sato, M. Sato, T. Seki, T. Shimozuma, M. Shoji, H. Suzuki, M. Takechi, Y. Takeiri, N. Tamura, K. Tanaka, K. Toi, T. Tokuzawa, Y. Torii, K. Tsumori, I. Yamada, S. Yamaguchi, S. Yamamoto, M. Yokoyama, Y. Yoshimura, K. Y. Watanabe, T. Watari, K. Itoh, K. Matsuoka, K. Ohkubo, I. Ohtake, S. Satoh, T. Satow, S. Sudo, S. Tanahashi, K. Yamazaki, Y. Hamada, O. Motojima, M. Fujiwara

研究成果: Contribution to journalConference article査読

2 被引用数 (Scopus)

抄録

In the Large Helical Device (LHD), upgrading of the key hardware system since the last EPS conference has led to (1) higher Te (Te(0) = 4.4 keV at 〈ne〉 = 5.3×1018 m-3 and Pabs = 1.8 MW); (2) higher confinement (τE = 0.3 s, Te(0) = 1.1 keV at 〈ne〉 = 6.5×1019 m-3 and Pabs = 2.0 MW); (3) higher stored energy Wpdia = 880 kJ; and (4) the highest β value in helical devices (2.4% at B = 1.3 T). The energy confinement was systematically higher than that predicted by the International Stellarator Scaling 95 up to a factor of 1.6. Ion cyclotron range of frequencies (ICRF) power up to 1.3 MW was reliably injected into the plasma without significant impurity contamination and a plasma with stored energy of 200 kJ was sustained for 5 s by ICRF alone. Long pulse discharges greater than 1 min in duration have been successfully achieved with ICRF power alone and with neutral beam injection (NBI) power alone. With NBI heating an 80 s discharge was achieved with a heating power of 0.5 MW at 2.75 T. The electron density was maintained at around 1.6×1019 m-3 by controlled gas puffing. The central electron and ion temperatures were kept around 1.5 keV. With ICRF heating, a similar long pulse discharge was achieved for 68 s with a heating power of 0.85 MW. The sustained plasma parameters are: Wp approximately 110 kJ, Te(0) approximately Ti(0) = 2.0 keV and 〈ne〉 = 1.0×1019 m-3. During these discharges, no increase in radiation power has been observed.

本文言語英語
ページ(範囲)B51-B60
ジャーナルPlasma Physics and Controlled Fusion
42
12 SUPPL. B
DOI
出版ステータス出版済み - 12 2000
外部発表はい
イベント27th European Physical Society Conference on Controlled Fusion and Plasma Physics - Budapest, Hung
継続期間: 6 12 20006 16 2000

All Science Journal Classification (ASJC) codes

  • 原子力エネルギーおよび原子力工学
  • 凝縮系物理学

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