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

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

Sep 1999

adsabs.harvard.edu/cgi-bin/nph-data_query?bibcode=1999aipc..485..341b&link_type=abstract

The thirteenth topical conference on radio frequency power in plasmas. AIP Conference Proceedings, Volume 485, pp. 341-344 (199

Computer Science

2

Plasma Heating By Particle Beams, Tokamaks, Spherical Tokamaks, Theory, Design, And Computerized Simulation

Scientific paper

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 (PICH=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 qmin~=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 qmin>~2 and a larger shear reversal radius.

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