Scoping and sensitivity analyses for the Demonstration Tokamak Hybrid Reactor (DTHR)
The results of an extensive set of parametric studies are presented which provide analytical data of the effects of various tokamak parameters on the performance and cost of the DTHR (Demonstration Tokamak Hybrid Reactor). The studies were centered on a point design which is described in detail. Variations in the device size, neutron wall loading, and plasma aspect ratio are presented, and the effects on direct hardware costs, fissile fuel production (breeding), fusion power production, electrical power consumption, and thermal power production are shown graphically. The studies considered both ignition and beam-driven operations of DTHR and yielded results based on two empirical scaling laws presently used in reactor studies. Sensitivity studies were also made for variations in the following key parameters: the plasma elongation, the minor radius, the TF coil peak field, the neutral beam injection power, and the Z/sub eff/ of the plasma.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
- DOE Contract Number:
- EG-77-C-02-4544
- OSTI ID:
- 5997341
- Report Number(s):
- WFPS-TME-79-012; TRN: 79-021960
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
HYBRID REACTORS
COST
PERFORMANCE
SYSTEMS ANALYSIS
TOKAMAK TYPE REACTORS
ASPECT RATIO
BREEDING RATIO
MAGNET COILS
NEUTRAL ATOM BEAM INJECTION
PLASMA
SHAPE
SIZE
WALL LOADING
BEAM INJECTION
CONFIGURATION
CONVERSION RATIO
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
POWER DENSITY
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology