Plasma and Fusion Research
Volume 11, 2405034 (2016)
Regular Articles
- National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
Abstract
An innovative idea is proposed for enlarging the blanket space on the inboard side of the torus for the helical fusion reactor FFHR-d1. A set of sub-helical coils, named NITA coils, with opposite-directed current outside the main helical coils, effectively reduces the helical pitch parameter and enlarges the blanket space. Dependence of the blanket space and plasma volume on the effective helical pitch parameter is examined. The obtained magnetic surfaces and their properties are compared with that of the original configuration.
Keywords
helical fusion reactor, FFHR-d1, optimization of heliotron magnetic configuration, blanket space, NITA coil
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