Impact of heat deposition profile on global confinement of NBI heated plasmas in the LHD

H. Yamada, S. Murakami, K. Yamazaki, O. Kaneko, J. Miyazawa, R. Sakamoto, K. Y. Watanabe, K. Narihara, K. Tanaka, S. Sakakibara, M. Osakabe, B. J. Peterson, S. Morita, K. Ida, S. Inagaki, S. Masuzaki, T. Morisaki, G. Rewoldt, H. Sugama, N. NakajimaW. A. Cooper, T. Akiyama, N. Ashikawa, M. Emoto, H. Funaba, P. Goncharov, M. Goto, H. Idei, K. Ikeda, M. Isobe, K. Kawahata, H. Kawazome, K. Khlopenkov, T. Kobuchi, A. Komori, A. Kostrioukov, S. Kubo, R. Kumazawa, Y. Liang, T. Minami, S. Muto, T. Mutoh, Y. Nagayama, Y. Nakamura, H. Nakanishi, Y. Narushima, K. Nishimura, N. Noda, T. Notake, H. Nozato, S. Ohdachi, N. Ohyabu, Y. Oka, T. Ozaki, A. Sagara, T. Saida, K. Saito, M. Sasao, K. Sato, M. Sato, T. Seki, T. Shimozuma, M. Shoji, H. Suzuki, Y. Takeiri, N. Takeuchi, N. Tamura, K. Toi, T. Tokuzawa, Y. Torii, K. Tsumori, T. Watanabe, T. Watari, Y. Xu, I. Yamada, S. Yamamoto, T. Yamamoto, M. Yokoyama, Y. Yoshimura, M. Yoshinuma, T. Mito, K. Itoh, K. Ohkubo, I. Ohtake, T. Satow, S. Sudo, T. Uda, K. Matsuoka, O. Motojima

研究成果: ジャーナルへの寄稿学術誌査読

36 被引用数 (Scopus)


Energy confinement and heat transport of net-current-free NBI heated plasmas in the large helical device (LHD) are discussed with emphasis on density and power deposition profile dependences. Although the apparent density dependence of the energy confinement time has been demonstrated in a wide parameter range in LHD, the loss of this dependence has been observed in the high density regime under specific conditions. Broad heat deposition due to off-axis alignment and shallow penetration of neutral beams degrades the global energy confinement while the local heat transport maintains a clear temperature dependence, lying between Bohm and gyro-Bohm characteristics. The central heat deposition tends towards an intrinsic density dependence like τE ∝ (n̄e/P)0.6 from the state where density dependence is lost. The broadening of the temperature profile due to the broad heat deposition profile contrasts with the invariant property that has been observed widely as profile resilience or stiffness in tokamak experiments. The confinement improvement as a result of the inward shift of the magnetic axis is obvious in the core region, which emphasizes the improvement of transport because of the geometry being unfavourable for the central heating of NBI in this configuration. The edge pressure, clearly, does not depend on the magnetic axis position. Unlike a tokamak H-mode, the edge pressure is determined by transport and can be increased by increasing the heating power.

ジャーナルNuclear Fusion
出版ステータス出版済み - 8月 2003

!!!All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 凝縮系物理学


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