Plasma and Fusion Research
Volume 9, 3403089 (2014)
Regular Articles
- National Institute for Fusion Science, Toki 509-5292, Japan
Abstract
We studied the optimization of the magnetic configuration for the LHD-type fusion energy reactor (FFHR). We propose thin and flat helical coil systems, which are partitioned to three blocks with independent current value control, to satisfy the following requirements: (1) sufficient blanket space and large plasma volume under the helical coils with appropriate major radius and (2) divertor legs with little disorder that turn to the back of the helical coils. The cross-section of the plasma boundary changes from elliptical to racetrack-type. By extending the coil height, the coil current density of the central block for helical coil is observed to decrease gradually.
Keywords
LHD, FFHR, configuration optimization, large blanket space
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This paper may be cited as follows:
Tsuguhiro WATANABE, Nagato YANAGI and Akio SAGARA, Plasma Fusion Res. 9, 3403089 (2014).