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Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices
KTH, Superseded Departments, Alfvén Laboratory.ORCID iD: 0000-0001-9901-6296
2003 (English)In: Vacuum, ISSN 0042-207X, E-ISSN 1879-2715, Vol. 70, no 03-feb, 423-428 p.Article in journal (Refereed) Published
Abstract [en]

Application of ion beam analysis techniques in the studies of material transport and fuel inventory in the controlled fusion devices is exemplified. Enhanced proton scattering on the carbon isotopes C-12(p,p)C-12, C-13(p,p)C-13 and secondary ion mass spectrometry allowed for determination of carbon erosion and re-deposition on the wall components following the experiments with a tracer ((CH4)-C-13) injection into the plasma edge at the TEXTOR tokamak. For the assessment of the deuterium fuel accumulation in the plasma facing components depth profiling by means of nuclear reaction analysis, He-3(d,p)He-4, was performed. Advantages and limitations of those nuclear methods in solving experimental problems are addressed.

Place, publisher, year, edition, pages
2003. Vol. 70, no 03-feb, 423-428 p.
Keyword [en]
ion beam analysis, erosion, deposition, hydrogen inventory, tokamak, deuterium, erosion, textor, penetration, deposition, surfaces, limiters
Identifiers
URN: urn:nbn:se:kth:diva-22353DOI: 10.1016/S0042-207X(02)00681-4ISI: 000181736800057OAI: oai:DiVA.org:kth-22353DiVA: diva2:341051
Note
QC 20100525Available from: 2010-08-10 Created: 2010-08-10 Last updated: 2017-12-12Bibliographically approved

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Rubel, Marek J.

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