K. Ida, M. Osakabe, K. Tanaka, T. Minami,
S. Nishimura, S. Okamura, A. Fujisawa, K. Yamazaki,
Y. Yoshimura, S. Kubo, R. Akiyama,
D. S. Darrow1, H. Idei,. H. Iguchi, M. Isobe,
S. Kado, T. Kondo2, S. Lee, K. Matsuoka,
S. Morita, I. Nomura, S. Ohdachi, M. Sasao,
A. Shimizu3, K. Tumori, S. Takayama2,
M. Takechi3, S. Takagi3, C. Takahashi,
K. Toi, T. Watari
National Institute for Fusion Science, Oroshi-cho, Toki-shi,
Gifu, 509-5292, Japan
1 Princeton Plasma Physics Laboratory, Princeton, NJ 08543, U.S.A.
2 Graduate University for Advanced Studies, Hayama, 240-01, Japan
3 Dept. Energy Engineering Science, Nagoya Univ., Nagoya, 464-01, Japan
Abstract. A high ion temperature mode (high
Ti mode) is observed for
neutral beam heated plasmas in the Compact Helical System (CHS)
Heliotron/torsatron. The high
Ti mode plasma is characterized by a
high central ion temperature,
Ti(0), and is associated with a peaked
electron density profile produced by neutral beam fueling with low wall
recycling. Transition from L mode to high
Ti mode has been studied in
CHS. The central ion temperature in the high
Ti mode discharges
reaches to 1 keV which is 2.5 times higher than that in the L mode
discharges. The ion thermal diffusivity is significantly reduced by a factor
of more than 2-3 in the high
Ti mode plasma. The ion loss cone is
observed in neutral particle flux in the energy range of 1-6 keV with a
narrow range of pitch angle (90 ± 10 degree) in the high
Ti mode.
However, the degradation of ion energy confinement due to this loss cone is
negligible.
IAEA 2001