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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, Shuichi Satoh, T. Satow, H. Tamura, S. Tanahashi, S. Yamaguchi, J. Yamamoto

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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.

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What this paper is about

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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Available 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.

Key concepts: Large Helical Device, Superconducting magnet, Fusion power, Plasma, Nuclear engineering, Superconductivity, Magnet, Toroid

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