NIFS-299

FULL TEXT (PDF, 372 KB)


Author(s):

K. Toi, T. Morisaki, S. Sakakibara, A. Ejiri, H. Yamada, S. Morita, K. Tanaka, N. Nakajima, S. Okamura, H. Iguchi, K. Ida, K. Tsumori, S. Ohdachi, K. Nishimura, K. Matsuoka, J. Xu, I. Yamada, T. Minami, K. Narihara, R. Akiyama, A. Ando, H. Arimoto, A. Fujisawa, M. Fujiwara, H. Idei, O. Kaneko, K. Kawahata, A. Komori, S. Kubo, R. Kumazawa,
T. Ozaki, A. Sagara, C. Takahashi, Y. Takita and T. Watari

Title:

Impact of Rotational-Transform Profile Control on Plasma Confinement and Stability in CHS

Date of publication:

Aug. 1994

Key words:

L-H Transition, Heliotron/Torsatron, Transport Barrier, Threshold Power, Rotational Transform, Density Fluctuations

Abstract:

In neutral beam heated plasma of CHS, which is a low aspect-ratio heliotron/torsatron device, the effect of rotational transform (chi) profile shape on plasma confinement and stability is studied by inducing a net plasma current (Ip). In the case that the external chi is increased by Ip, very rapid H-mode transition (within ~0.2 ms) is observed at the thresholds of Ip and heating power, having all characteristics found in the tokamak H-mode. There is no obvious difference in the H-mode characteristics between deuterium and hydrogen plasmas. In the opposite case that the external chi is decreased by reversing Ip, the H-mode transition is not observed.

List of NIFS Report (1994)Return toContents Page Return toNIFS Homepage
footer
 National Institute for Fusion Science
Copyright: 1995-2007 National Institute for Fusion Science (NIFS)
Address: 322-6,Oroshi-cho, Toki, GIFU, 509-5292, Japan
Telephone:+81-572-58-2222