Driven magnetic reconnection in the COMPASS-C tokamak
- AEA Fusion, Culham Laboratory (UKAEA/Euratom Fusion Association), Abingdon, Oxon (United Kingdom)
The question of the influence of nonaxisymmetric field perturbations on tokamaks is investigated. Recent experiments in the COMPASS-C tokamak (in {ital Proceedings} {ital of} {ital the} 15{ital th} {ital Symposium} {ital on} {ital Fusion} {ital Technology}, Utrecht (North-Holland, Amsterdam, 1989), Vol. 1, p. 361) with externally applied helical fields reveal that magnetic islands do not appear until the applied field exceeds a certain value, when plasma rotation and confinement are affected. A new resistive magnetohydrodynamic model including plasma rotation now provides an explanation of this threshold, and is quantitatively consistent with experimental results in Ohmic plasmas. The results indicate the tolerable error fields in future tokamaks. The effects of perturbations with various poloidal and toroidal mode numbers have been studied.
- OSTI ID:
- 5130835
- Journal Information:
- Physics of Fluids B; (United States), Vol. 4:2; ISSN 0899-8221
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
TOKAMAK DEVICES
MAGNETIC RECONNECTION
HELICAL CONFIGURATION
ION TEMPERATURE
MAGNETIC ISLANDS
MAGNETOHYDRODYNAMICS
OHM LAW
PLASMA CONFINEMENT
PLASMA MACROINSTABILITIES
ROTATING PLASMA
THERMONUCLEAR REACTORS
TOROIDAL CONFIGURATION
ANNULAR SPACE
CLOSED CONFIGURATIONS
CLOSED PLASMA DEVICES
CONFIGURATION
CONFINEMENT
FLUID MECHANICS
HYDRODYNAMICS
INSTABILITY
MAGNETIC FIELD CONFIGURATIONS
MECHANICS
PLASMA
PLASMA INSTABILITY
SPACE
THERMONUCLEAR DEVICES
700340* - Plasma Waves
Oscillations
& Instabilities- (1992-)