Control of Internal Profiles via LHCD on Alcator C-Mod

Journal Article · Thu Nov 26 00:00:00 EST 2009 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.3273759· OSTI ID:21335736

Wilson, J R; Kessel, C; Scott, S; Wallace, G M ^[1]; Parker, R R; Bonoli, P T; Hubbard, A E; Hughes, J W; Ince-Cushman, A; Ko, J S; Meneghini, O; Porkolab, M; Reinke, M; Rice, J E; Schmidt, A E; Shiraiwa, S; Wright, J C ^[2]

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1. Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543 (United States)
2. MIT Plasma Science and Fusion Center, Cambridge, MA 02139 (United States)

LHCD on Alcator C-Mod is being used in plasmas with parameters similar to those expected on ITER for the purpose of tailoring the plasma current profile. LHCD experiments have also produced intriguing results related to momentum transport and edge pedestal physics that affect the toroidal rotation profile and the temperature and density profiles. Quantitative comparisons between local measurements and theory/simulation have been performed, confirming the off-axis localization of the current drive, as well as its magnitude and location dependence on the launched n{sub parallel} spectrum and electron temperature. Applying LHCD during the current ramp saves volt-seconds and delays the peaking of the current profile. Counter current toroidal rotation during LHCD has been observed in both L and H-mode plasmas. In H-mode plasmas the edge pedestal collisionality is reduced while the overall pressure in the pedestal increases slightly.

• OSTI ID: 21335736
• Journal Information: AIP Conference Proceedings, Vol. 1187, Issue 1; Conference: 18. topical conference on radio frequency power in plasmas, Gent (Belgium), 24-26 Jun 2009; Other Information: DOI: 10.1063/1.3273759; (c) 2009 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ABSORPTION
ALCATOR DEVICE
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONTROL
COUNTER CURRENT
ELECTRIC CURRENTS
ELECTRON TEMPERATURE
H-MODE PLASMA CONFINEMENT
ITER TOKAMAK
L-MODE PLASMA CONFINEMENT
LOWER HYBRID CURRENT DRIVE
PLASMA
PLASMA DENSITY
PLASMA SIMULATION
ROTATION
WAVEGUIDES