Overview of confinement and MHD stability in the Large Helical Device

O. Motojima, K. Ida, K. Y. Watanabe, Y. Nagayama, A. Komori, T. Morisaki, B. J. Peterson, Y. Takeiri, K. Ohkubo, K. Tanaka, T. Shimozuma, S. Inagaki, T. Kobuchi, S. Sakakibara, J. Miyazawa, H. Yamada, N. Ohyabu, K. Narihara, K. Nishimura, M. YoshinumaS. Morita, T. Akiyama, N. Ashikawa, C. D. Beidler, M. Emoto, T. Fujita, T. Fukuda, H. Funaba, P. Goncharov, M. Goto, T. Ido, K. Ikeda, A. Isayama, M. Isobe, H. Igami, K. Ishii, K. Itoh, O. Kaneko, K. Kawahata, H. Kawazome, S. Kubo, R. Kumazawa, S. Masuzaki, K. Matsuoka, T. Minami, S. Murakami, S. Muto, T. Mutoh, Y. Nakamura, H. Nakanishi, Y. Narushima, M. Nishiura, A. Nishizawa, N. Noda, T. Notake, H. Nozato, S. Ohdachi, Y. Oka, S. Okajima, M. Osakabe, T. Ozaki, A. Sagara, T. Saida, K. Saito, M. Sakamoto, R. Sakamoto, Y. Sakamoto, M. Sasao, K. Sato, M. Sato, T. Seki, M. Shoji, S. Sudo, N. Takeuchi, H. Takenaga, N. Tamura, K. Toi, T. Tokuzawa, Y. Torii, K. Tsumori, T. Uda, A. Wakasa, T. Watari, I. Yamada, S. Yamamoto, K. Yamazaki, M. Yokoyama, Y. Yoshimura

研究成果: Contribution to journalArticle査読

34 被引用数 (Scopus)

抄録

The Large Helical Device is a heliotron device with L ≤ 2 and M ≤ 10 continuous helical coils with a major radius of 3.5-4.1 m, a minor radius of 0.6 m and a toroidal field of 0.5-3 T, which is a candidate among toroidal magnetic confinement systems for a steady state thermonuclear fusion reactor. There has been significant progress in extending the plasma operational regime in various plasma parameters by neutral beam injection with a power of 13 MW and electron cyclotron heating (ECH) with a power of 2 MW. The electron and ion temperatures have reached up to 10 keV in the collisionless regime, and the maximum electron density, the volume averaged beta value and stored energy are 2.4 × 1020 m-3, 4.1% and 1.3 MJ, respectively. In the last two years, intensive studies of the magnetohydrodynamics stability providing access to the high beta regime and of healing of the magnetic island in comparison with the neoclassical tearing mode in tokamaks have been conducted. Local island divertor experiments have also been performed to control the edge plasma aimed at confinement improvement. As for transport study, transient transport analysis was executed for a plasma with an internal transport barrier and a magnetic island. The high ion temperature plasma was obtained by adding impurities to the plasma to keep the power deposition to the ions reasonably high even at a very low density. By injecting 72 kW of ECH power, the plasma was sustained for 756 s without serious problems of impurities or recycling.

本文言語英語
ページ(範囲)S255-S265
ジャーナルNuclear Fusion
45
10
DOI
出版ステータス出版済み - 10 1 2005
外部発表はい

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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