OEDGE modeling of the DIII-D H-mode 13CH4 puffing experiment

J. D. Elder*, A. G. McLean, P. C. Stangeby, S. L. Allen, J. A. Boedo, B. D. Bray, N. H. Brooks, M. E. Fenstermacher, M. Groth, A. W. Leonard, D. Reiter, D. L. Rudakov, W. R. Wampler, J. G. Watkins, W. P. West, D. G. Whyte

*Corresponding author for this work

Research output: Contribution to journalArticleScientificpeer-review

16 Citations (Scopus)


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.

Original languageEnglish
Pages (from-to)140-145
Number of pages6
JournalJournal of Nuclear Materials
Publication statusPublished - 15 Jun 2007
MoE publication typeA1 Journal article-refereed


  • C0100
  • Carbon impurities
  • D0500
  • DIII-D
  • Edge modeling
  • I0100
  • Impurity transport
  • P0600
  • T0100


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