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Modeling of erosion and deposition patterns on C-W and W-Ta twin limiters exposed to the TEXTOR edge plasmas
KTH, Superseded Departments, Alfvén Laboratory.ORCID iD: 0000-0001-9901-6296
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2004 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 329-33, 732-736 p.Article in journal (Refereed) Published
Abstract [en]

The erosion and deposition patterns on tungsten and tantalum test limiters exposed to the TEXTOR deuterium plasma containing a small amount of C impurity are simulated with the modified EDDY code. At the very top of the W and Ta limiters, there occurs neither erosion nor deposition, but the erosion proceeds slowly along the surface. When approaching the edge, the surface is covered by a thick C layer, which shows a very sharp boundary similar to the observation in surface measurements. In the erosion zone, the re-deposited carbon forms a W (Ta)-C mixed layer with small C concentration. Assumptions for chemical erosion yields of similar to0.01 for W and

Place, publisher, year, edition, pages
2004. Vol. 329-33, 732-736 p.
Keyword [en]
tungsten, implantation, release
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-23672DOI: 10.1016/j.jnucmat.2004.04.183ISI: 000223505000139Scopus ID: 2-s2.0-3342995293OAI: oai:DiVA.org:kth-23672DiVA: diva2:342371
Note
QC 20100525 QC 20110926. 11th International Conference on Fusion Reactor Materials (ICFRM). Kyoto, JAPAN. DEC 07-12, 2003 Available from: 2010-08-10 Created: 2010-08-10 Last updated: 2011-10-19Bibliographically approved

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Rubel, Marek J.

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