Comparison between the electron cyclotron current drive experiments on DIII-D and predictions for T-10

Conference · Thu Nov 01 00:00:00 EST 1990

OSTI ID:6169810

Lohr, J; Harvey, R W; Luce, T C; Matsuda, Kyoko; Moeller, C P; Petty, C C; Prater, R ^[1]; James, R A ^[2]; Giruzzi, G ^[3]; Gorelov, Y ^[4]; DeHaas, J ^[5]

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1. General Atomics, San Diego, CA (USA)
2. Lawrence Livermore National Lab., CA (USA)
3. Association Euratom-CEA, Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
4. Kurchatov Inst. of Atomic Energy, Moscow (USSR)
5. Joint European Torus Un

Electron cyclotron current drive has been demonstrated on the DIII-D tokamak in an experiment in which {approximately}1 MW of microwave power generated {approximately}50 kA of non-inductive current. The rf-generated portion was about 15% of the total current. On the T-10 tokamak, more than 3 MW of microwave power will be available for current generation, providing the possibility that all the plasma current could be maintained by this method. Fokker-Planck calculations using the code CQL3D and ray tracing calculations using TORAY have been performed to model both experiments. For DIII-D the agreement between the calculations and measurements is good, producing confidence in the validity of the computational models. The same calculations using the T-10 geometry predict that for n{sub e}(0) {approximately} 1.8 {times} 10{sup 13} cm{sup {minus}3}, and T{sub e}(0) {approximately} 7 keV, 1.2 MW, that is, the power available from only three gyrotrons, could generate as much as 150 kA of non-inductive current. Parameter space scans in which temperature, density and resonance location were varied have been performed to indicate the current drive expected under different experimental conditions. The residual dc electric field was considered in the DIII-D analysis because of its nonlinear effect on the electron distribution, which complicates the interpretation of the results. A 110 GHz ECH system is being installed on DIII-D. Initial operations, planned for late 1991, will use four gyrotrons with 500 kW each and 10 second output pulses. Injection will be from the low field side from launchers which can be steered to heat at the desired location. These launchers, two of which are presently installed, are set at 20 degrees to the radial and rf current drive studies are planned for the initial operation. 8 refs., 10 figs.

• Research Organization: General Atomics, San Diego, CA (USA); Lawrence Livermore National Lab., CA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC03-89ER51114; W-7405-ENG-48
• OSTI ID: 6169810
• Report Number(s): GA-A-20276; CONF-9009118-1; ON: DE91005396; TRN: 91-001246
• Resource Relation: Conference: International workshop on strong microwaves in plasmas, Suzdal (USSR), 18-23 Sep 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DOUBLET REACTORS
NON-INDUCTIVE CURRENT DRIVE
COMPARATIVE EVALUATIONS
T-10 TOKAMAK
CALCULATION METHODS
ECR HEATING
ELECTRON DENSITY
ELECTRON TEMPERATURE
FOKKER-PLANCK EQUATION
TEMPERATURE DEPENDENCE
CLOSED PLASMA DEVICES
DIFFERENTIAL EQUATIONS
EQUATIONS
HEATING
HIGH-FREQUENCY HEATING
PARTIAL DIFFERENTIAL EQUATIONS
PLASMA HEATING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production
700205 - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems