Plasma engineering analysis of a small torsatron reactor
This study examines the plasma physics and reactor engineering feasibility of a small, medium aspect ratio, high-beta, l = 2, D-T torsatron power reactor, based on the magnetic configuration of the Advanced Toroidal Facility, Oak Ridge National Laboratory. Plasma analyses are performed to assess whether confinement in a small, average radius plasma is sufficient to yield an ignited or high-Q driven device. Much of the physics assessment focuses on an evaluation of the radial electric field created by the nonambipolar particle flux. Detailed transport simulations are done with both fixed and self-consistent evolution of the radial electric field. Basic reactor engineering considerations taken into account are neutron wall loading, maximum magnetic field at the helical coils, coil shield thickness, and tritium breeding blanket-shield thickness.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5111353
- Report Number(s):
- ORNL/TM-9533; ON: DE86001469
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
BREEDING BLANKETS
CLOSED PLASMA DEVICES
DESIGN
DIMENSIONS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ENGINEERING
EQUIPMENT
MAGNET COILS
POWER PLANTS
REACTOR COMPONENTS
SHIELDING
STELLARATORS
THERMONUCLEAR DEVICES
THERMONUCLEAR POWER PLANTS
THICKNESS
TORSATRON STELLARATOR
700200* -- Fusion Energy-- Fusion Power Plant Technology
BREEDING BLANKETS
CLOSED PLASMA DEVICES
DESIGN
DIMENSIONS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ENGINEERING
EQUIPMENT
MAGNET COILS
POWER PLANTS
REACTOR COMPONENTS
SHIELDING
STELLARATORS
THERMONUCLEAR DEVICES
THERMONUCLEAR POWER PLANTS
THICKNESS
TORSATRON STELLARATOR