Plasma and Fusion Research
Volume 7, 2402072 (2012)
Regular Articles
- National Institute for Fusion Science, Toki, Gifu 509-5292, Japan
Abstract
The performance of high-density plasmas heated by neutral beam (NB) injection in a vertically elongated configuration using four poloidal coils has been investigated in LHD and shown to be better than that in the normal configuration using six poloidal coils. Reduction of poloidal coils is favorable in designing an LHD-type helical reactor FFHR-d1, from both points of view of cost reduction and realization of large maintenance ports. In the experiment, no clear difference between the two configurations was recognized in the relation between the central density and the central pressure. Meanwhile, a factor Cexp used in the direct profile extrapolation (DPE) method is smaller in the vertically elongated configuration, where Cexp is proportional to the reactor size, Rreactor, at a given reactor magnetic field, Breactor, i.e., Rreactor ∝ CexpBreactor−4/3. The difference in Cexp between the two configurations is enhanced to > 10 % as the plasma beta increases. This might be due to the larger plasma volume and/or the mitigated Shafranov shift in the vertically elongated configuration.
Keywords
heliotron, LHD, FFHR-d1, energy confinement scaling, vertical elongation, reactor design
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This paper may be cited as follows:
Junichi MIYAZAWA, Takuya GOTO, Ryuichi SAKAMOTO, Gen MOTOJIMA, Chihiro SUZUKI, Tomohiro MORISAKI, Suguru MASUZAKI, Ichihiro YAMADA, Hiroshi YAMADA, Akio SAGARA and the FFHR Design Group, Plasma Fusion Res. 7, 2402072 (2012).