Impact of a poloidal divertor in ignition tokamak design
- ORNL
- Grumman Aerospace
- Science Applications International Corporation (SAIC), Oak Ridge, TN
- McDonnell Douglas Aerospace
- University of Tennessee, Knoxville (UTK)
System design studies were performed to assess the effect of assuming a poloidal divertor instead of a limiter as a means of impurity control for ignition tokamak configurations. Results show that for the nominal Tokamak Fusion Core Experiment (TFCX) device with superconducting TF coils, a feasible poloidal divertor configuration can be obtained without increasing the major radius. In the TFCX nominal copper TF coil device, however, field limits at the PF coils are exceeded when the effects of asymmetry associated with a poloidal divertor are included. It was found that a 12% increase in the major radius of this device is necessary to simultaneously satisfy the plasma-shaping requirements of a poloidal divertor and the magnetics constraints at the superconducting PF coils.
- Research Organization:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Organization:
- SC USDOE - Office of Science (SC)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1024764
- Journal Information:
- Fusion Technology, Journal Name: Fusion Technology Journal Issue: 1 Vol. 8; ISSN 0748-1896; ISSN FUSTE8
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ASYMMETRY
COMPARATIVE EVALUATIONS
CONFINEMENT
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
FEASIBILITY STUDIES
MAGNET COILS
MAGNETIC FIELD CONFIGURATIONS
MAGNETS
PLASMA CONFINEMENT
POLOIDAL FIELD DIVERTORS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
SYSTEMS ANALYSIS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS