Erosion/redeposition analysis: status of modeling and code validation for semi-detached tokamak edge plasmas

Citation
Jn. Brooks et al., Erosion/redeposition analysis: status of modeling and code validation for semi-detached tokamak edge plasmas, J NUCL MAT, 269, 1999, pp. 58-66
Citations number
27
Categorie Soggetti
Apllied Physucs/Condensed Matter/Materiales Science","Nuclear Emgineering
Journal title
JOURNAL OF NUCLEAR MATERIALS
ISSN journal
00223115 → ACNP
Volume
269
Year of publication
1999
Pages
58 - 66
Database
ISI
SICI code
0022-3115(199903)269:<58:EASOMA>2.0.ZU;2-W
Abstract
We are analyzing erosion and tritium codeposition for ITER, DIII-D, and oth er devices with a focus on carbon divertor and metallic wall sputtering, fo r detached and semi-detached edge plasmas. Carbon chemical-sputtering/hydro carbon-transport is computed in detail using upgraded models for sputtering yields, species, and atomic and molecular processes. For the DIII-D analys is this includes proton impact and dissociative recombination for the fun m ethane and higher hydrocarbon chains. Several mixed material (Si-C doping a nd Be/C) effects on erosion are examined. A semi-detached reactor plasma re gime yields peak net wall erosion rates of similar to 1.0 (Be), similar to 0.3 (Fe), and similar to 0.01 CN) cm/burn-yr, and similar to 50 cm/burn-yr for a carbon divertor. Net carbon erosion is dominated by chemical sputteri ng in the similar to 1-3 eV detached plasma zone. Tritium codeposition in d ivertor-sputtered redeposited carbon is high (similar to 10-20 g T/1000 s). Silicon and beryllium mixing tends to reduce carbon erosion. Initial hydro carbon transport calculations for the DIII-D DiMES-73 detached plasma exper iment show a broad spectrum of redeposited molecules with similar to 90% re deposition fraction. (C) 1999 Elsevier Science B.V. All rights reserved.