Simulations of ICRF-fast wave current drive on DIIID
Self-consistent calculations of MHD equilibria, generated by fast wave current drive and including the bootstrap effect, were done to guide and anticipate the results of upcoming experiments on the DIIID tokamak. The simulations predict that 2 MW of ICRF power is more than adequate to create several hundred kiloamperes in steady state; the total current increases with the temperature and density of the target plasma. 12 refs., 12 figs., 1 tab.
- Research Organization:
- Argonne National Lab., IL (USA). Fusion Power Program
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6757087
- Report Number(s):
- ANL/FPP/TM-248; ON: DE90013634; TRN: 90-027100
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DOUBLET REACTORS
NON-INDUCTIVE CURRENT DRIVE
BOOTSTRAP CURRENT
CURRENT DENSITY
ELECTRON TEMPERATURE
ICR HEATING
MHD EQUILIBRIUM
PLASMA SIMULATION
POWER DENSITY
TEMPERATURE DISTRIBUTION
CURRENTS
ELECTRIC CURRENTS
EQUILIBRIUM
HEATING
HIGH-FREQUENCY HEATING
PLASMA HEATING
SIMULATION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production
DOUBLET REACTORS
NON-INDUCTIVE CURRENT DRIVE
BOOTSTRAP CURRENT
CURRENT DENSITY
ELECTRON TEMPERATURE
ICR HEATING
MHD EQUILIBRIUM
PLASMA SIMULATION
POWER DENSITY
TEMPERATURE DISTRIBUTION
CURRENTS
ELECTRIC CURRENTS
EQUILIBRIUM
HEATING
HIGH-FREQUENCY HEATING
PLASMA HEATING
SIMULATION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production