Recent studies of the large helical device

Journal Article · Fri Sep 01 04:00:00 EDT 1995 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.49034· OSTI ID:279516

Iiyoshi, A; Yamazaki, K ^[1]

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

The Large Helical Device (LHD) is presently under construction (1990{endash}1997) in NIFS, Japan. The magnetic configuration is chosen as an optimized heliotron with double helix coils, succeeding Heliotron-E, ATF and CHS. Target plasma parameters of the LHD with fully superconducting coil systems are; {ital n}{tau}{sub {ital ET}}{approximately}10{sup 20} m{sup {minus}3}{center_dot}s{center_dot}keV, {bar {beta}}=5{percent} and steady operations with {ital R}{sub {ital p}}=3.75 m, {ital a}{sub {ital p}}=50{endash}65 cm, and {ital B}{sub 0}=3{endash}4 T. The major objectives of the LHD project are to demonstrate good plasma confinement, high beta achievement, and steady-state divertor operation in the helical system. Various R&D results have been obtained on superconducting coils, negative ion source, and special diagnostics for LHD. In our new site (Toki-city, Gifu-prefecture), the construction of the main experimental hall of the LHD Building was finished, and the winding of the helical coil has been started there. The construction of LHD will be completed in 1997. {copyright} {ital 1995 American Institute of Physics.}

• Sponsoring Organization: USDOE
• OSTI ID: 279516
• Report Number(s): CONF-9410130--
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 345; ISSN 0094-243X; ISSN APCPCS
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DESIGN
DIVERTORS
HELICAL CONFIGURATION
MAGNETIC SURFACES
OPTIMIZATION
PLASMA CONFINEMENT
STEADY-STATE CONDITIONS
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTIONS