Design, development and operation of superconducting system for LHD

T. Mito; A. Nishimura; S. Yamada; S. Imagawa; K. Takahata; N. Yanagi; R. Maekawa; H. Chikaraishi; H. Tamura; A. Iwamoto; S. Hamaguchi; Y. Hishinuma; T. Satow; O. Motojima

Design, development and operation of superconducting system for LHD

T. Mito, A. Nishimura, S. Yamada, S. Imagawa, K. Takahata, N. Yanagi, R. Maekawa, H. Chikaraishi, H. Tamura, A. Iwamoto, S. Hamaguchi, Y. Hishinuma, T. Satow, O. Motojima

Research output: Contribution to conference › Paper › peer-review

7 Scopus citations

Abstract

The Large Helical Device (LHD) of National Institute for Fusion Science (NIFS) is a heliotron-type experimental fusion device which has the capability of confining current-less and steady-state plasma. The primary feature on the engineering aspect of LHD is using superconducting coils for magnetic confinement: two pool boiling helical coils (H1, H2) and three pairs of forced-flow poloidal coils (IV, IS, OV) wound with cable-in-conduit conductors (CICC). The maximum magnetic field at plasma center is 3 T in Phase I experiment and 4 T in Phase II, while its stored energy becomes 0.9 GJ and 1.6 GJ, respectively. These coils are connected to the power supplies by superconducting bus-lines with their nominal current of 31.3 kA. The construction of LHD started in 1991 and was completed by the end of 1997. During this period, extensive research and development were conducted to complete a large-scale superconducting system. The plasma experiment started on March 31, 1998 and four plasma experimental campaigns have been performed successfully in three years. The fifth cycle operation started in August 2001. The knowledge which has been acquired during the design, development, and operation of superconducting system for LHD, is summarized.

Original language	English
Pages	144-151
Number of pages	8
State	Published - 2002
Externally published	Yes
Event	19th IEEE/NPSS Symposium on Fusion Engineering (19th SOFE) - Atlantic City, NJ, United States Duration: Jan 22 2002 → Jan 25 2002

Conference

Conference	19th IEEE/NPSS Symposium on Fusion Engineering (19th SOFE)
Country/Territory	United States
City	Atlantic City, NJ
Period	01/22/02 → 01/25/02

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This output contributes to the following UN Sustainable Development Goals (SDGs)

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Mito, T., Nishimura, A., Yamada, S., Imagawa, S., Takahata, K., Yanagi, N., Maekawa, R., Chikaraishi, H., Tamura, H., Iwamoto, A., Hamaguchi, S., Hishinuma, Y., Satow, T., & Motojima, O. (2002). Design, development and operation of superconducting system for LHD. 144-151. Paper presented at 19th IEEE/NPSS Symposium on Fusion Engineering (19th SOFE), Atlantic City, NJ, United States.

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title = "Design, development and operation of superconducting system for LHD",

abstract = "The Large Helical Device (LHD) of National Institute for Fusion Science (NIFS) is a heliotron-type experimental fusion device which has the capability of confining current-less and steady-state plasma. The primary feature on the engineering aspect of LHD is using superconducting coils for magnetic confinement: two pool boiling helical coils (H1, H2) and three pairs of forced-flow poloidal coils (IV, IS, OV) wound with cable-in-conduit conductors (CICC). The maximum magnetic field at plasma center is 3 T in Phase I experiment and 4 T in Phase II, while its stored energy becomes 0.9 GJ and 1.6 GJ, respectively. These coils are connected to the power supplies by superconducting bus-lines with their nominal current of 31.3 kA. The construction of LHD started in 1991 and was completed by the end of 1997. During this period, extensive research and development were conducted to complete a large-scale superconducting system. The plasma experiment started on March 31, 1998 and four plasma experimental campaigns have been performed successfully in three years. The fifth cycle operation started in August 2001. The knowledge which has been acquired during the design, development, and operation of superconducting system for LHD, is summarized.",

author = "T. Mito and A. Nishimura and S. Yamada and S. Imagawa and K. Takahata and N. Yanagi and R. Maekawa and H. Chikaraishi and H. Tamura and A. Iwamoto and S. Hamaguchi and Y. Hishinuma and T. Satow and O. Motojima",

year = "2002",

language = "English",

pages = "144--151",

note = "19th IEEE/NPSS Symposium on Fusion Engineering (19th SOFE) ; Conference date: 22-01-2002 Through 25-01-2002",

}

Mito, T, Nishimura, A, Yamada, S, Imagawa, S, Takahata, K, Yanagi, N, Maekawa, R, Chikaraishi, H, Tamura, H, Iwamoto, A, Hamaguchi, S, Hishinuma, Y, Satow, T & Motojima, O 2002, 'Design, development and operation of superconducting system for LHD', Paper presented at 19th IEEE/NPSS Symposium on Fusion Engineering (19th SOFE), Atlantic City, NJ, United States, 01/22/02 - 01/25/02 pp. 144-151.

TY - CONF

T1 - Design, development and operation of superconducting system for LHD

AU - Mito, T.

AU - Nishimura, A.

AU - Yamada, S.

AU - Imagawa, S.

AU - Takahata, K.

AU - Yanagi, N.

AU - Maekawa, R.

AU - Chikaraishi, H.

AU - Tamura, H.

AU - Iwamoto, A.

AU - Hamaguchi, S.

AU - Hishinuma, Y.

AU - Satow, T.

AU - Motojima, O.

PY - 2002

Y1 - 2002

N2 - The Large Helical Device (LHD) of National Institute for Fusion Science (NIFS) is a heliotron-type experimental fusion device which has the capability of confining current-less and steady-state plasma. The primary feature on the engineering aspect of LHD is using superconducting coils for magnetic confinement: two pool boiling helical coils (H1, H2) and three pairs of forced-flow poloidal coils (IV, IS, OV) wound with cable-in-conduit conductors (CICC). The maximum magnetic field at plasma center is 3 T in Phase I experiment and 4 T in Phase II, while its stored energy becomes 0.9 GJ and 1.6 GJ, respectively. These coils are connected to the power supplies by superconducting bus-lines with their nominal current of 31.3 kA. The construction of LHD started in 1991 and was completed by the end of 1997. During this period, extensive research and development were conducted to complete a large-scale superconducting system. The plasma experiment started on March 31, 1998 and four plasma experimental campaigns have been performed successfully in three years. The fifth cycle operation started in August 2001. The knowledge which has been acquired during the design, development, and operation of superconducting system for LHD, is summarized.

AB - The Large Helical Device (LHD) of National Institute for Fusion Science (NIFS) is a heliotron-type experimental fusion device which has the capability of confining current-less and steady-state plasma. The primary feature on the engineering aspect of LHD is using superconducting coils for magnetic confinement: two pool boiling helical coils (H1, H2) and three pairs of forced-flow poloidal coils (IV, IS, OV) wound with cable-in-conduit conductors (CICC). The maximum magnetic field at plasma center is 3 T in Phase I experiment and 4 T in Phase II, while its stored energy becomes 0.9 GJ and 1.6 GJ, respectively. These coils are connected to the power supplies by superconducting bus-lines with their nominal current of 31.3 kA. The construction of LHD started in 1991 and was completed by the end of 1997. During this period, extensive research and development were conducted to complete a large-scale superconducting system. The plasma experiment started on March 31, 1998 and four plasma experimental campaigns have been performed successfully in three years. The fifth cycle operation started in August 2001. The knowledge which has been acquired during the design, development, and operation of superconducting system for LHD, is summarized.

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M3 - Paper

AN - SCOPUS:0036366159

SP - 144

EP - 151

T2 - 19th IEEE/NPSS Symposium on Fusion Engineering (19th SOFE)

Y2 - 22 January 2002 through 25 January 2002

ER -

Design, development and operation of superconducting system for LHD

Abstract

Conference

UN SDGs

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