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Author(s):
A. Iiyoshi and K. Yamazaki
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Title:
The Next Large Helical Devices
Date of publication:
Nov. 1994
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Key words:
LHD, Wendelstein 7-X, helical system, heliotron, stellarator, superconducting magnet
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Abstract:
Helical systems have strong merits of steady-state operations 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, major radius = 3.9m, magnetic field =3-4T, under construction during 1990-1997) in NIFS (National Institute for Fusion Science)-Nagoya/Toki, Japan, which provides with continuous helical coils and clean helical divertor focusing on edge configuration optimization. The other one is the W7-X (Wendelstein 7-X, major radius = 5.5m, magnetic field = 3T, under approval) in MPIPP(Max-Planck Institute for Plasma Physics)-Garching, Germany, which adopted a modular coil system after elaborate optimization studies of core plasma physics. These two programs are complementary to promote world helical fusion research and to extend the comprehensive understanding of toroidal plasmas by comparing with large tokamaks.
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