Thermal loads on tokamak plasma facing components during normal operation and disruptions
Power loadings experienced by tokamak plasma facing components during normal operation and during off-normal events are discussed. A model for power and particle flow in the tokamak boundary layer is presented and model predictions are compared to infrared measurements of component heating. The inclusion of the full three-dimensional geometry of the component and of the magnetic flux surface is very important in the modeling. Experimental measurements show that misalignment of component armor tile surfaces by only a millimeter can lead to significant localized heating. An application to the design of plasma facing components for future machines is presented. Finally, thermal loads expected during tokamak disruptions are discussed. The primary problems are surface melting and vaporization due to localized intense heating during the disruption thermal quench and volumetric heating of the component armor and structure due to localized impact of runaway electrons. 39 refs., 8 figs., 1 tab.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5577815
- Report Number(s):
- SAND-89-2064C; CONF-890906-4; ON: DE90000794; TRN: 89-026084
- Resource Relation:
- Journal Volume: 41; Journal Issue: 4-6; Conference: 11. international vacuum congress and 7th international conference on solid surfaces, Cologne (Germany, F.R.), 25-29 Sep 1989
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
TOKAMAK DEVICES
WALL LOADING
BOUNDARY LAYERS
DIVERTORS
HEAT FLUX
LIMITERS
MAGNETIC SURFACES
OPERATION
PLASMA DISRUPTION
PLASMA HEATING
CLOSED PLASMA DEVICES
HEATING
LAYERS
MAGNETIC FIELD CONFIGURATIONS
POWER DENSITY
THERMONUCLEAR DEVICES
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production
700209 - Fusion Power Plant Technology- Component Development & Materials Testing