OEDGE Modeling of the DIII-D H-Mode 13CH4 Puffing Experiment [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 2006.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: PDF-file: 18 pages; size: 0.6 Mbytes
Additional Creators:: Lawrence Berkeley National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

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 toroidally 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 to 20 m/s (+ R-direction) were found to yield ¹³C deposition comparable to the experiment.

Report Numbers:

E 1.99:ucrl-jrnl-221818
ucrl-jrnl-221818

Subject(s):

Plasma Physics And Fusion

Other Subject(s):

Note:

Published through SciTech Connect.
06/01/2006.
"ucrl-jrnl-221818"
Journal of Nuclear Materials, vol. 363-365, N/A, June 15, 2007, pp. 140-145 363-365 ISSN 0022-3115; JNUMAM FT
Allen, S L; Watkins, J G; Leonard, A W; McLean, A G; Bray, B D; Wampler, W R; West, W P; Elder, J D; Reiter, D; Stangeby, P C; Fenstermacher, M E; Rudakov, D L; Boedo, J C; Whyte, D G; Brooks, N H; Groth, M.

Funding Information:

W-7405-ENG-48

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