Large helical device (LHD) program

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. TamuraA. 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

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56 Citations (Scopus)

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.

Original languageEnglish
Pages (from-to)7-153
Number of pages147
JournalJournal of Fusion Energy
Volume15
Issue number1-2
DOIs
Publication statusPublished - 1996 Jan 1
Externally publishedYes

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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