RF current profile control studies in the alcator C-mod tokamak

Journal Article · Mon Sep 20 04:00:00 EDT 1999 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.59764· OSTI ID:20216703

Bonoli, P T ^[1]; Porkolab, M ^[1]; Wukitch, S J ^[1]; Bernabei, S ^[2]; Kaita, R ^[2]; Mikkelsen, D ^[2]; Phillips, C K ^[2]; Schilling, G ^[2]

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1. MIT PSFC, Cambridge, Massachusetts 02139 (United States)
2. PPPL, Princeton University, Princeton, New Jersey 08543 (United States)

Time dependent calculations of lower hybrid (LH) current profile control in Alcator C-Mod have been done using the TRANSP [1], FPPRF [2], and LSC [3] codes. Up to 3 MW of LH current drive power was applied in plasmas with high power ICRF minority heating (P{sub ICH}=1.8-3 MW) and fast current ramp up. Using the experimentally measured temperature profiles, off-axis current generation resulted in nonmonotonic q-profiles with q{sub min}{approx_equal}1.6. Self-consistent effects of off-axis electron heating by the LH power were also included in the analysis and significant broadening of the electron temperature profile was found with q{sub min}(greater-or-similar sign)2 and a larger shear reversal radius. (c) 1999 American Institute of Physics.

• OSTI ID: 20216703
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 485; ISSN 0094-243X; ISSN APCPCS
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CURRENT DENSITY
ELECTRON TEMPERATURE
ICR HEATING
POWER RANGE 01-10 MW
TEMPERATURE DISTRIBUTION
THEORETICAL DATA
TOKAMAK TYPE REACTORS