Electron Cyclotron Heating and Current Drive Results from the DIII-D Tokamak

Conference · Mon Oct 01 00:00:00 EDT 1990

OSTI ID:6194869

Luce, T. C. ^[1]; James, R. A. ^[2]; Fyaretdinov, A. ^[3]; de Gentile, B. ^[4]; Giruzzi, G ^[4]; Gorelov, Yu ^[3]; deHaas, J. ^[2]; Harvey, R. ^[1]; Janz, S. ^[5]; Lohr, John ^[1]; Prater, R. ^[1]; Rodriguez, L. ^[4]; Saigusa, M. ^[6]; Snider, R. ^[1]; Stallard, B. ^[1]; Stockdale, R. ^[1]; Trukhin, V ^[3]

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1. General Atomics, San Diego, CA (United States)
2. Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
3. National Research Centre, Moscow (Russian Federation). Kurchatov Institute
4. CEN, Cadarache (France)
5. Univ. of Maryland, College Park, MD (United States)
6. Japan Atomic Energy Research Inst. (JAERI), Tokai (Japan)

Auxiliary heating experiments with electron cyclotron heating have been carried out in the DIII-D tokamak. Waves at 60 GHz have been launched at power levels up to 1.4 MW from both the high-field and low-field side with the appropriate polarization for damping at the fundamental resonance (2.14 T). Confinement was studied in L-mode and H-mode plasmas for a single-null, open divertor geometry. For L-mode discharges, the energy confinement scaling agrees well with the ITER-89 power law or offset linear scaling relations. With strong off-axis heating, the electron temperature profile remains peaked, and power balance analysis indicates that the transport cannot be described by a purely diffusive model. In H-mode confinement plasmas, the magnitude and scaling of the confinement time are equal to that of plasmas heated by neutral beam injection (NBI), if the energy stored in the fast ions is removed in the NBI cases. A major issue for steady-state H-mode plasmas is control of the edge-localized mode (ELM) behavior. By moving the resonance location ±5 cm around the separatrix, the frequency of giant ELMs can be changed by a factor of three. Non-inductive current drive with electron cyclotron waves has also been investigated. Driven currents up to 70 kA have been observed, but the current drive is enhanced by the residual dc electric field. Currents aiding and opposing the Ohmic current have been measured. The magnitude of the current for co-current drive is greater than expected from modeling which includes trapped particle effects, but no electric field. Preliminary calculations including the residual dc electric field can account for the observed enhancement.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: AC03-89ER51114
• OSTI ID: 6194869
• Report Number(s): GA-A-20281; CONF-901025-44; IAEA-CN-53/E-1-2; ON: DE91008922; TRN: 91-006743
• Resource Relation: Conference: 13. International Conference on Plasma Physics and Controlled Nuclear Fusion Research, Washington, DC (United States), 1-6 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DOUBLET REACTORS
ECR HEATING
BEAM INJECTION HEATING
CONFINEMENT TIME
CURRENT-DRIVE HEATING
ELECTRON TEMPERATURE
H-MODE PLASMA CONFINEMENT
PLASMA INSTABILITY
CONFINEMENT
ELECTRIC HEATING
HEATING
HIGH-FREQUENCY HEATING
INSTABILITY
JOULE HEATING
PLASMA CONFINEMENT
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production