Tilt and shift mode stability in a spheromak with a flux core
The stability of spheromak equilibria with a flux core, or reversal coil, is studied by means of an ideal MHD code. Results depend critically upon whether the flux hole region (the current free area just inside the separatrix) is treated as perfectly conducting plasma or as vacuum. This indicates that the tilt and shift modes persist as resistive instabilities if they are stable in ideal MHD. Specifically, for nonoptimally shaped equilibria, the flux core must nearly touch the current channel if the flux hole is vacuum, whereas the core may be slightly outside the separatrix if the flux hole has conducting plasma. A larger margin exists for optimally shaped equilibria.
- Research Organization:
- Princeton Univ., NJ (USA). Plasma Physics Lab.
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 6713041
- Report Number(s):
- PPPL-2121; ON: DE84015149
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700107* -- Fusion Energy-- Plasma Research-- Instabilities
CLOSED PLASMA DEVICES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUILIBRIUM PLASMA
EQUIPMENT
FLUID MECHANICS
HYDRODYNAMICS
INSTABILITY
MAGNET COILS
MAGNETOHYDRODYNAMICS
MECHANICS
PLASMA
PLASMA INSTABILITY
PLASMA MACROINSTABILITIES
SPHEROMAK DEVICES
THERMONUCLEAR DEVICES
TILTING INSTABILITY
TOKAMAK DEVICES
700107* -- Fusion Energy-- Plasma Research-- Instabilities
CLOSED PLASMA DEVICES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUILIBRIUM PLASMA
EQUIPMENT
FLUID MECHANICS
HYDRODYNAMICS
INSTABILITY
MAGNET COILS
MAGNETOHYDRODYNAMICS
MECHANICS
PLASMA
PLASMA INSTABILITY
PLASMA MACROINSTABILITIES
SPHEROMAK DEVICES
THERMONUCLEAR DEVICES
TILTING INSTABILITY
TOKAMAK DEVICES