Improved plasma performance on Large Helical Device

A. Komori, N. Ohyabu, H. Yamada, O. Kaneko, K. Kawahata, N. Ashikawa, P. DeVaries, M. Emoto, H. Funaba, M. Goto, K. Ida, H. Idei, K. Ikeda, S. Inagaki, N. Inoue, M. Isobe, S. Kado, K. Khlopenkov, T. Kobuchi, S. KuboR. Kumazawa, Y. Liang, S. Masuzaki, Y. Matsumoto, T. Minami, J. Miyazawa, T. Morisaki, S. Morita, S. Murakami, S. Muto, T. Mutoh, Y. Nagayama, Y. Nakamura, H. Nakanishi, K. Narihara, Y. Narushima, K. Nishimura, N. Noda, T. Notake, S. Ohdachi, Y. Oka, M. Okamoto, 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. Watanabe, T. Watari, Y. Hamada, K. Itoh, K. Matsuoka, K. Ohkubo, T. Satow, S. Sudo, K. Yamazaki, O. Motojima, M. Fujiwara

研究成果: ジャーナルへの寄稿会議記事査読

15 被引用数 (Scopus)


Since the start of the Large Helical Device (LHD) experiment, various attempts have been made to achieve improved plasma performance in LHD [A. Iiyoshi et al., Nucl. Fusion 39, 1245 (1999)]. Recently, an inward-shifted configuration with a magnetic axis position Rax of 3.6 m has been found to exhibit much better plasma performance than the standard configuration with Rax of 3.75 m. A factor of 1.6 enhancement of energy confinement time was achieved over the International Stellarator Scaling 95. This configuration has been predicted to have unfavorable magnetohydrodynamic (MHD) properties, based on linear theory, even though it has significantly better particle-orbit properties, and hence lower neoclassical transport loss. However, no serious confinement degradation due to the MHD activities was observed, resolving favorably the potential conflict between stability and confinement at least up to the realized volume-averaged beta 〈β〉 of 2.4%. An improved radial profile of electron temperature was also achieved in the configuration with magnetic islands, minimized by an external perturbation coil system for the Local Island Divertor (LID). The LID has been proposed for remarkable improvement of plasma confinement like the high (H) mode in tokamaks, and the LID function was suggested in limiter experiments.

ジャーナルPhysics of Plasmas
5 II
出版ステータス出版済み - 5月 2001
イベント42nd Annual Meeting of the APS Division of Plasma Physics - Quebec, Que, カナダ
継続期間: 10月 23 200010月 27 2000

!!!All Science Journal Classification (ASJC) codes

  • 凝縮系物理学


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