Current profile control for ITER with rf current drive
- Argonne National Lab., IL (United States)
- Lawrence Livermore National Lab., CA (United States)
Self-consistent MHD equilibria are found with the RIP computer code, which traces lower hybrid and fast wave rays in two dimensions; the tokamak flux surfaces are generated by LHCD, FWCD and the bootstrap effect. The bootstrap current dominates at the mid-minor radius, the FWCD provides the seed current and LHCD is effective only in the surface region of a fusion-grade tokamak. The bootstrap fraction maximizes by operating at high central safety factor, q (0) {approx} 2, that is, with rather minimal FWCD; while the total current is effectively controlled by LHCD. There is potentially considerable flexibility to affect the current profile and MHD stability by appropriate adjustments to the RF power spectra. Current drive on ITER is more attractive at higher aspect ratios, and results are presented for A = 4.0. 6 refs.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5183195
- Report Number(s):
- ANL/CP-73548; CONF-910869-5; ON: DE91018597
- Resource Relation:
- Conference: 9. topical conference on radio frequency power in plasmas, Charleston, SC (United States), 12-14 Aug 1991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ITER TOKAMAK
BOOTSTRAP CURRENT
LOWER HYBRID CURRENT DRIVE
ASPECT RATIO
CONTROL
MHD EQUILIBRIUM
CLOSED PLASMA DEVICES
CURRENTS
ELECTRIC CURRENTS
EQUILIBRIUM
NON-INDUCTIVE CURRENT DRIVE
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production