Plasma and Fusion Research
Volume 5, S2029 (2010)
Regular Articles
- National Institute of Fusion Science, Toki 509-5292, Japan
Abstract
Improvement of ion heat transport was observed in the core plasma heated by neutral beam injection (NBI) in the Large Helical Device (LHD). A peaked ion temperature profile with a steep gradient (an ion internal transport barrier, ion ITB) formed in the plasma. To investigate the formation conditions of the ion ITB, a simple definition of ITB based on the reversal of the temperature gradient between the core and the edge is proposed. An ion ITB formed in the low-collisionality regime of 1/ν with low density and high ion heating power in the LHD.
Keywords
ion heat transport, ion internal transport barrier, gradient reversal
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This paper may be cited as follows:
Kenichi NAGAOKA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Shigeru MORITA, Naoki TAMURA, Takeshi IDO, Akihiro SHIMIZU, Katsunori IKEDA, Masaki OSAKABE, Katsuyoshi TSUMORI, Haruhisa NAKANO and LHD Experiment Group, Plasma Fusion Res. 5, S2029 (2010).