Fusion control studies: interim report on divertor and gas blanket impurity control study
A simple calculational model for the transport of particles across the scrape off region between the plasma and the wall in the presence of a divertor or a gas blanket has been developed. The variation of the divertor or gas blanket performance as a function of the heat and particle fluxes escaping from the plasma, the wall material and the cross field diffusion is examined and numerical examples are given. This work contributes to an understanding of the divertor and gas blanket parameters that are required in order to efficiently shield the plasma and it also helps to indicate new methods for improving the effectiveness of divertors and gas blankets.
- Research Organization:
- Georgia Inst. of Tech., Atlanta (USA). School of Nuclear Engineering
- DOE Contract Number:
- ET-78-S-05-5683
- OSTI ID:
- 5923786
- Report Number(s):
- GTFR-8
- Country of Publication:
- United States
- Language:
- English
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