Superconducting magnet system of large helical device

O. Motojima; N. Yanagi; S. Imagawa; K. Takahata; S. Yamada; R. Maekawa; H. Chikaraishi; A. Iwamoto; S. Masuzaki; T. Mito; T. Morisaki; A. Nishimura; S. Satoh; T. Satow; H. Tamura; al et al

doi:10.13182/fst96-a11963116

Superconducting magnet system of large helical device

O. Motojima, N. Yanagi, S. Imagawa, K. Takahata, S. Yamada, R. Maekawa, H. Chikaraishi, A. Iwamoto, S. Masuzaki, T. Mito, T. Morisaki, A. Nishimura, S. Satoh, T. Satow, H. Tamura, al et al

Research output: Contribution to journal › Conference article › peer-review

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Abstract

The Large Helical Device is a superconducting toroidal device for the fusion research which has a maximum stored energy of 1.6 GJ (4 T at the plasma center). The LHD has l/m = 2/10 superconducting helical coils and three sets of poloidal coils. The plasma performance expected is equivalent to a Q value (fusion out put/heating power) from 0.1 to 0.3. Since the LHD plasma is currentless, it provides a useful and reliable data base for the steady-state operation without any danger of plasma current disruptions. Therefore, the superconductivity is a key technology in this project. Results of research and development for the superconducting (SC) magnet system of the LHD is reported.

Original language	English
Pages (from-to)	1226-1233
Number of pages	8
Journal	Unknown Journal
Volume	30
Issue number	3
DOIs	https://doi.org/10.13182/fst96-a11963116
State	Published - 1996
Externally published	Yes
Event	Proceedings of the 1996 12th Topical Meeting on the Technology of Fusion Energy. Part 2 (of 2) - Reno, NV, USA Duration: Jun 16 1996 → Jun 20 1996

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10.13182/fst96-a11963116

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title = "Superconducting magnet system of large helical device",

abstract = "The Large Helical Device is a superconducting toroidal device for the fusion research which has a maximum stored energy of 1.6 GJ (4 T at the plasma center). The LHD has l/m = 2/10 superconducting helical coils and three sets of poloidal coils. The plasma performance expected is equivalent to a Q value (fusion out put/heating power) from 0.1 to 0.3. Since the LHD plasma is currentless, it provides a useful and reliable data base for the steady-state operation without any danger of plasma current disruptions. Therefore, the superconductivity is a key technology in this project. Results of research and development for the superconducting (SC) magnet system of the LHD is reported.",

author = "O. Motojima and N. Yanagi and S. Imagawa and K. Takahata and S. Yamada and R. Maekawa and H. Chikaraishi and A. Iwamoto and S. Masuzaki and T. Mito and T. Morisaki and A. Nishimura and S. Satoh and T. Satow and H. Tamura and {et al}, al",

year = "1996",

doi = "10.13182/fst96-a11963116",

language = "English",

volume = "30",

pages = "1226--1233",

journal = "Unknown Journal",

number = "3",

note = "Proceedings of the 1996 12th Topical Meeting on the Technology of Fusion Energy. Part 2 (of 2) ; Conference date: 16-06-1996 Through 20-06-1996",

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TY - JOUR

T1 - Superconducting magnet system of large helical device

AU - Motojima, O.

AU - Yanagi, N.

AU - Imagawa, S.

AU - Takahata, K.

AU - Yamada, S.

AU - Maekawa, R.

AU - Chikaraishi, H.

AU - Iwamoto, A.

AU - Masuzaki, S.

AU - Mito, T.

AU - Morisaki, T.

AU - Nishimura, A.

AU - Satoh, S.

AU - Satow, T.

AU - Tamura, H.

AU - et al, al

PY - 1996

Y1 - 1996

N2 - The Large Helical Device is a superconducting toroidal device for the fusion research which has a maximum stored energy of 1.6 GJ (4 T at the plasma center). The LHD has l/m = 2/10 superconducting helical coils and three sets of poloidal coils. The plasma performance expected is equivalent to a Q value (fusion out put/heating power) from 0.1 to 0.3. Since the LHD plasma is currentless, it provides a useful and reliable data base for the steady-state operation without any danger of plasma current disruptions. Therefore, the superconductivity is a key technology in this project. Results of research and development for the superconducting (SC) magnet system of the LHD is reported.

AB - The Large Helical Device is a superconducting toroidal device for the fusion research which has a maximum stored energy of 1.6 GJ (4 T at the plasma center). The LHD has l/m = 2/10 superconducting helical coils and three sets of poloidal coils. The plasma performance expected is equivalent to a Q value (fusion out put/heating power) from 0.1 to 0.3. Since the LHD plasma is currentless, it provides a useful and reliable data base for the steady-state operation without any danger of plasma current disruptions. Therefore, the superconductivity is a key technology in this project. Results of research and development for the superconducting (SC) magnet system of the LHD is reported.

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U2 - 10.13182/fst96-a11963116

DO - 10.13182/fst96-a11963116

M3 - Conference article

AN - SCOPUS:0030074075

VL - 30

SP - 1226

EP - 1233

JO - Unknown Journal

JF - Unknown Journal

IS - 3

T2 - Proceedings of the 1996 12th Topical Meeting on the Technology of Fusion Energy. Part 2 (of 2)

Y2 - 16 June 1996 through 20 June 1996

ER -

Superconducting magnet system of large helical device

Abstract

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