ITER equilibrium with bootstrap currents, lower hybrid current drive and fast wave current drive
A current drive system is proposed for the technology phase of ITER which relies on rf power and bootstrap currents. The rf/bootstrap system permits operation at high safety factor, and we consider the axial value to be q/sub a/ approx. = 1.9, which minimizes the need for seed current near the magnetic axis. Lower hybrid power (/approximately/30 MW) provides current density near the surface, ICRF (/approximately/65 MHz, /approximately/30 MW) fast waves generate current near the axis, and high frequency fast waves (/approximately/250 MHz, /approximately/74 MW) supply the remaining current density. The system is not yet optimized but appears to offer great flexibility (ion heating for ignition, current rampup, etc.) with relatively inexpensive and well developed technology. 29 refs., 16 figs., 1 tab.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6313660
- Report Number(s):
- ANL/FPP/TM-238; ON: DE89009676; TRN: 89-011007
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Current generation by helicons and lower hybrid waves in modern tokamaks and reactors ITER and DEMO. Scenarios, modeling and antennae
60 MHz fast wave current drive experiments for DIII-D
Related Subjects
TOKAMAK TYPE REACTORS
CURRENT-DRIVE HEATING
CURRENT DENSITY
ICR HEATING
LOWER HYBRID HEATING
MHD EQUILIBRIUM
RF SYSTEMS
ELECTRIC HEATING
EQUILIBRIUM
HEATING
HIGH-FREQUENCY HEATING
JOULE HEATING
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR REACTORS
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production