Erosion/redeposition analysis : status of modeling and code validation for semi-detached tokamak edge plasmas.
We are analyzing erosion and tritium codeposition for ITER, DIII-D, and other devices with a focus on carbon divertor and metallic wall sputtering, for detached and semi-detached edge plasmas. Carbon chemical-sputtering hydrocarbon-transport is computed in detail using upgraded models for sputtering yields, species, and atomic and molecular processes. For the DIII-D analysis this includes proton impact and dissociative recombination for the full methane and higher hydrocarbon chains. Several mixed material (Si-C doping and Be/C) effects on erosion are examined. A semi-detached reactor plasma regime yields peak net wall erosion rates of {approximately}1.0 (Be), {approximately}0.3 (Fe), and {approximately}0.01 (W) cm/burn-yr, and {approximately}50 cm/burn-yr for a carbon divertor. Net carbon erosion is dominated by chemical sputtering in the {approximately}1-3 eV detached plasma zone. Tritium codeposition in divertor-sputtered redeposited carbon is high ({approximately}10-20 g-T/1000 s ). Silicon and beryllium mixing tends to reduce carbon erosion. Initial hydrocarbon transport calculations for the DIII-D DiMES-73 detached plasma experiment show a broad spectrum of redeposited molecules with {approximately}90% redeposition fraction.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10811
- Report Number(s):
- ANL/TD/CP-96490
- Country of Publication:
- United States
- Language:
- English
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