Computational studies of impurity effects, impurity control, and neutral beam injection in large tokamaks
Computational models have been constructed for the Princeton Large Torus (PLT), the Poloidal Divertor Experiment (PDX), and the Tokamak Fusion Test Reactor (TFTR). These models have been calibrated by comparison with current experiments and used to predict plasma parameters and delineate favorable modes of operation for future experiments. The models for PLT emphasize plasma transport and neutral beam injection heating. The models for PDX emphasize the capability of divertors for impurity and recycling control in intense neutral-beam-heated tokamaks, as well as optimization of the MHD properties of divertor-equipped tokamaks. The TFTR calculations stress the fusion aspects of a large, circular cross-section D-T tokamak with intense neutral beam injection.
- Research Organization:
- Princeton Univ., NJ (USA). Plasma Physics Lab.; California Univ., Livermore (USA). Lawrence Livermore Lab.
- DOE Contract Number:
- EY-76-C-02-3073
- OSTI ID:
- 6532280
- Report Number(s):
- PPPL-1476; CONF-780811-30; IAEA-CN-37-F-3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700105* -- Fusion Energy-- Plasma Research-- Plasma Kinetics-Theoretical-- (-1987)
BEAM INJECTION
CONTROL
DIVERTORS
IMPURITIES
NEUTRAL ATOM BEAM INJECTION
PDX DEVICES
PLASMA DRIFT
PLT REACTORS
TFTR REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSPORT THEORY