Design status of superconducting large helical device

Conference · Fri Mar 01 04:00:00 EST 1991 · IEEE Transactions on Magnetics (Institute of Electrical and Electronics Engineers); (United States)

OSTI ID:6044284

Motojima, O ^[1]

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1. National Inst. for Fusion Science, Furo-cho, Chikusa-ku, Nagoya 464-01 (JP)

This paper reports on large Helical Device (LHD) which is a superconducting heliotron/torsatron type device. The SC coil system is composed of {ell} = 2 helical coils and 3 sets of poloidal coils with a total stored magnetic energy of 1.63 GJ. The main machine parameters, m number, {ell} number, major radius, coil minor radius, magnetic field, plasma minor radius, and plasma volume are 10, 2, 3.9 m, 0.975 m, 4 T, 0.65 m, and 30 m{sup 3}, respectively. This is an alternative toroidal device which aims at producing plasmas extrapolatable to the reactor regime. The currentless steady operation is the final goal of our LHD program, and there is no danger from the major current disruptions. The material of the super-conductor is NbTi, and the cooling systems are pool-boiling for helical coils and forced-flow for poloidal coils.

• OSTI ID: 6044284
• Report Number(s): CONF-900944--
• Conference Information: Journal Name: IEEE Transactions on Magnetics (Institute of Electrical and Electronics Engineers); (United States) Journal Volume: 27:2
• Country of Publication: United States
• Language: English

Related Subjects

665412 -- Superconducting Devices-- (1992-)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700430* -- Fusion Technology-- Magnet Coils & Fields-- (1992-)
75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
ALLOYS
BOILING
CLOSED PLASMA DEVICES
CONFIGURATION
CONFINEMENT
CONSTRUCTION
COOLING SYSTEMS
DESIGN
DIVERTORS
HELICAL CONFIGURATION
MAGNETIC FIELDS
NIOBIUM ALLOYS
PHASE TRANSFORMATIONS
PLASMA RADIAL PROFILES
POOL BOILING
SUPERCONDUCTING COILS
THERMONUCLEAR DEVICES
TITANIUM ALLOYS