Article ID Journal Published Year Pages File Type
1569167 Journal of Nuclear Materials 2007 6 Pages PDF
Abstract

Use of carbon in tokamaks leads to a serious tritium retention issue due to co-deposition. To further investigate the processes involved, a detached ELMy H-mode (6.5 MW NBI) experiment was performed on DIII-D in which 13CH4 was puffed into the main vessel through the toroidaly symmetric pumping plenum at the top of lower single-null discharges. Subsequently, the 13C content of tiles taken from the vessel wall was measured. The interpretive OEDGE code was used to model the results. The 13C deposition pattern could be reproduced, in general shape and magnitude, by assuming in the code the existence of a parallel flow and a radial pinch in the scrape-off layer. Parallel flows of Mach ∼0.3 toward the inner divertor and a radial pinch ∼10–20 m/s (+R-direction) were found to yield 13C deposition comparable to the experiment.

Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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