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, Inagaki Shigeru, 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

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36 Citations (Scopus)


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.

Original languageEnglish
Pages (from-to)S255-S265
JournalNuclear Fusion
Issue number10
Publication statusPublished - Oct 1 2005
Externally publishedYes

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Condensed Matter Physics


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