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Large Helical Device (LHD) program

Authors :
Fujiwara, M.
Yamazaki, K.
Okamoto, M.
Todoroki, J.
Amano, T.
Watanabe, T.
Hayashi, T.
Sanuki, H.
Nakajima, N.
Itoh, K.
Sugama, H.
Ichiguchi, K.
Murakami, S.
Motojima, O.
Yamamoto, J.
Satow, T.
Yanagi, N.
Imagawa, S.
Takahata, K.
Tamura, H.
Nishimura, A.
Komori, A.
Inoue, N.
Noda, N.
Sagara, A.
Kubota, Y.
Akaishi, N.
Satoh, S.
Tanahashi, S.
Chikaraishi, H.
Mito, T.
Yamada, S.
Yamaguchi, S.
Sudo, S.
Sato, K.
Watari, T.
Kuroda, T.
Kaneko, O.
Ohkubo, K.
Kitagawa, S.
Ando, A.
Idei, H.
Tsumori, K.
Kubo, S.
Kumazawa, R.
Mutoh, T.
Oka, Y.
Sato, M.
Seki, T.
Shimozuma, T.
Takeiri, Y.
Hamada, Y.
Narihara, K.
Kawahata, K.
Fujisawa, S.
Hidekuma, S.
Minami, T.
Yamada, I.
Ejiri, A.
Tanaka, K.
Sasao, M.
Iguchi, H.
Watanabe, K.
Yamada, H.
Ohyabu, N.
Suzuki, H.
Iiyoshi, A.
Source :
Journal of Fusion Energy; June 1996, Vol. 15 Issue: 1-2 p7-153, 147p
Publication Year :
1996

Abstract

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.

Details

Language :
English
ISSN :
01640313 and 15729591
Volume :
15
Issue :
1-2
Database :
Supplemental Index
Journal :
Journal of Fusion Energy
Publication Type :
Periodical
Accession number :
ejs14959456
Full Text :
https://doi.org/10.1007/BF02266926