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Large Helical Device (LHD) program

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Abstract

The largest superconducting fusion machine, Large Helical Device (LHD), is now under construction in Japan and will begin operation in 1997. Design and construction of related R&D programs are now being carried out. The major radius of this machine is 3.9 m and the magnetic field on the plasma center is 3 T. The NbTi superconducting conductors are used in both helical coils and poloidal coils to produce this field. This will be upgraded in the second phase a using superfluid coil cooling technique. A negative ion source is being successfully developed for the NBI heating of LHD. This paper describes the present status and progress in its experimental planning and theoretical analysis on LHD, and the design and construction of LHD torus, heating, and diagnostics equipments.

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Author notes

  1. M. Fujiwara, K. Yamazaki, M. Okamoto, J. Todoroki, T. Amano, T. Watanabe, T. Hayashi, H. Sanuki, N. Nakajima, K. Itoh, H. Sugama, K. Ichiguchi, S. Murakami, O. Motojima, J. Yamamoto, T. Satow, N. Yanagi, S. Imagawa, K. Takahata, H. Tamura, A. Nishimura, A. Komori, N. Inoue, N. Noda, A. Sagara, Y. Kubota, N. Akaishi, S. Satoh, S. Tanahashi, H. Chikaraishi, T. Mito, S. Yamada, S. Yamaguchi, S. Sudo, K. N. Sato, T. Watari, T. Kuroda, O. Kaneko, K. Ohkubo, S. Kitagawa, A. Ando, H. Idei, K. Tsumori, S. Kubo, R. Kumazawa, T. Mutoh, Y. Oka, M. Sato, T. Seki, T. Shimozuma, Y. Takeiri, Y. Hamada, K. Narihara, K. Kawahata, S. Fujisawa, S. Hidekuma, T. Minami, I. Yamada, A. Ejiri, K. Tanaka, M. Sasao, H. Iguchi, K. Y. Watanabe, H. Yamada, N. Ohyabu, H. Suzuki & A. Iiyoshi

    Present address: National Institute for Fusion Science, Chikusa-ku, 464-01, Nagoya, Japan

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    Fujiwara, M., Yamazaki, K., Okamoto, M. et al. Large Helical Device (LHD) program. J Fusion Energ 15, 7–153 (1996). https://doi.org/10.1007/BF02266926

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