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Analysis of fuel retention in plasma-facing components from controlled fusion devices
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.ORCID iD: 0000-0001-9901-6296
2009 (English)In: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, ISSN 0168-583X, Vol. 267, no 4, 711-717 p.Article in journal (Refereed) Published
Abstract [en]

First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma-wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.

Place, publisher, year, edition, pages
Elsevier, 2009. Vol. 267, no 4, 711-717 p.
Keyword [en]
Controlled thermonuclear fusion, Wall materials, Retention, Deuterium, Tokamak
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-25587DOI: 10.1016/j.nimb.2008.11.035ISI: 000264739000036Scopus ID: 2-s2.0-61549138727OAI: oai:DiVA.org:kth-25587DiVA: diva2:370523
Conference
17th International Workshop on Inelastic Ion-Surface Collisions Porquerolles, FRANCE, SEP 21-26, 2008
Note
QC 20101117Available from: 2012-01-26 Created: 2010-10-27 Last updated: 2012-02-22Bibliographically approved

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Rubel, Marek J.

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