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. 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

doi:10.1007/BF02266926

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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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 language	English
Pages (from-to)	7-153
Number of pages	147
Journal	Journal of Fusion Energy
Volume	15
Issue number	1-2
DOIs	https://doi.org/10.1007/BF02266926
Publication status	Published - Jan 1 1996
Externally published	Yes

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

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10.1007/BF02266926

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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., ... Iiyoshi, A. (1996). Large helical device (LHD) program. Journal of Fusion Energy, 15(1-2), 7-153. https://doi.org/10.1007/BF02266926

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, KN, 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, KY, Yamada, H, Ohyabu, N, Suzuki, H & Iiyoshi, A 1996, 'Large helical device (LHD) program', Journal of Fusion Energy, vol. 15, no. 1-2, pp. 7-153. https://doi.org/10.1007/BF02266926

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title = "Large helical device (LHD) program",

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.",

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

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T1 - Large helical device (LHD) program

AU - Fujiwara, M.

AU - Yamazaki, K.

AU - Okamoto, M.

AU - Todoroki, J.

AU - Amano, T.

AU - Watanabe, T.

AU - Hayashi, T.

AU - Sanuki, H.

AU - Nakajima, N.

AU - Itoh, K.

AU - Sugama, H.

AU - Ichiguchi, K.

AU - Murakami, S.

AU - Motojima, O.

AU - Yamamoto, J.

AU - Satow, T.

AU - Yanagi, N.

AU - Imagawa, S.

AU - Takahata, K.

AU - Tamura, H.

AU - Nishimura, A.

AU - Komori, A.

AU - Inoue, N.

AU - Noda, N.

AU - Sagara, A.

AU - Kubota, Y.

AU - Akaishi, N.

AU - Satoh, S.

AU - Tanahashi, S.

AU - Chikaraishi, H.

AU - Mito, T.

AU - Yamada, S.

AU - Yamaguchi, S.

AU - Sudo, S.

AU - Sato, K. N.

AU - Watari, T.

AU - Kuroda, T.

AU - Kaneko, O.

AU - Ohkubo, K.

AU - Kitagawa, S.

AU - Ando, A.

AU - Idei, H.

AU - Tsumori, K.

AU - Kubo, S.

AU - Kumazawa, R.

AU - Mutoh, T.

AU - Oka, Y.

AU - Sato, M.

AU - Seki, T.

AU - Shimozuma, T.

AU - Takeiri, Y.

AU - Hamada, Y.

AU - Narihara, K.

AU - Kawahata, K.

AU - Fujisawa, S.

AU - Hidekuma, S.

AU - Minami, T.

AU - Yamada, I.

AU - Ejiri, A.

AU - Tanaka, K.

AU - Sasao, M.

AU - Iguchi, H.

AU - Watanabe, K. Y.

AU - Yamada, H.

AU - Ohyabu, N.

AU - Suzuki, H.

AU - Iiyoshi, A.

PY - 1996/1/1

Y1 - 1996/1/1

N2 - 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.

AB - 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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DO - 10.1007/BF02266926

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SN - 0164-0313

VL - 15

SP - 7

EP - 153

JO - Journal of Fusion Energy

JF - Journal of Fusion Energy

IS - 1-2

ER -

Large helical device (LHD) program

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