The next large helical devices

Helical systems have the strong advantage of inherent steady‐state operation for fusion reactors. Two large helical devices with fully superconducting coil systems are presently under design and construction. One is the LHD (Large Helical Device) [Fusion Technol. 17, 169 (1990)] with major radius=3....

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Bibliographic Details
Published in:Physics of plasmas 1995-06, Vol.2 (6), p.2349-2356
Main Authors: Iiyoshi, Atsuo, Yamazaki, Kozo
Format: Article
Language:English
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Summary:Helical systems have the strong advantage of inherent steady‐state operation for fusion reactors. Two large helical devices with fully superconducting coil systems are presently under design and construction. One is the LHD (Large Helical Device) [Fusion Technol. 17, 169 (1990)] with major radius=3.9 m and magnetic field=3–4 T, that is under construction during 1990–1997 at NIFS (National Institute for Fusion Science), Nagoya/Toki, Japan; it features continuous helical coils and a clean helical divertor focusing on edge configuration optimization. The other one in the W7‐X (Wendelstein 7‐X) [in Plasma Physics and Controlled Fusion Nuclear Research, 1990, (International Atomic Energy Agency, Vienna, 1991), Vol. 3, p. 525] with major radius=5.5 m and magnetic field=3 T, that is under review at IPP (Max‐Planck Institute for Plasma Physics), Garching, Germany; it has adopted a modular coil system after elaborate optimization studies. These two programs are complementary in promoting world helical fusion research and in extending the understanding of toroidal plasmas through comparisons with large tokamaks.
ISSN:1070-664X
1089-7674
DOI:10.1063/1.871260