Edge Minority Heating Experiment in Alcator C-Mod

Journal Article · Mon Sep 26 04:00:00 EDT 2005 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.2098207· OSTI ID:20726291

Zweben, S J; Budny, R; Perkins, R; Schilling, G ^[1]; Terry, J L; Bonoli, P; Fiore, C; Hughes, J; Lin, Y; Porkolab, M; Wukitch, S ^[2]; Chang, C S ^[3]

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1. Princeton Plasma Physics Laboratory, Princeton NJ 08540 (United States)
2. MIT, Cambridge, MA (United States)
3. New York University, New York (United States)

An attempt was made to control global plasma confinement in the Alcator C-Mod tokamak by applying ICRH heating power to the plasma edge in order to deliberately create a minority ion tail loss. In theory, an edge fast ion loss could modify the edge electric field and so stabilize the edge turbulence, which might then reduce the H-mode power threshold or improve the H-mode barrier. However, the experimental result was that edge minority heating resulted in no improvement in the edge plasma parameters or global stored energy, at least at power levels of PRF {<=} 5.5 MW. Some analysis of these results is presented and some ideas for improvement are discussed.

• OSTI ID: 20726291
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 787; ISSN 0094-243X; ISSN APCPCS
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ALCATOR DEVICE
CHARGED-PARTICLE TRANSPORT
ELECTRIC FIELDS
H-MODE PLASMA CONFINEMENT
ICR HEATING
IONS
PLASMA
RF SYSTEMS
TURBULENCE