Survey of dust formed in the TEXTOR tokamak: structure and fuel retention
2009 (English)In: Physica scripta. T, ISSN 0281-1847, Vol. T138, 014025- p.Article in journal (Refereed) Published
A detailed survey of erosion and deposition on plasma-facing components was performed in the TEXTOR tokamak. Co-deposits and dust particles were collected from graphite limiters and from several locations on the Inconel liner. The total amount of dust (loose material), originating mainly from carbon-rich co-deposits detached from the limiters and the liner, was around 2 g, with sizes from 0.1 mu m to 1 mm. The morphology and fuel retention was determined using microscopy methods, ion beam analysis and thermal desorption spectrometry. The study revealed differences in structure and fuel content between deposits from the toroidal and main poloidal limiters. There were also splashes, up to 1 mm in diameter, of molten metal (mainly nickel) on the toroidal limiters. Issues of the dust conversion factor (erosion-to-dust) are addressed and a comparison with results of previous dust surveys at TEXTOR is also briefly presented.
Place, publisher, year, edition, pages
Institute of Physics Publishing (IOPP), 2009. Vol. T138, 014025- p.
CONTROLLED FUSION DEVICES, CO-DEPOSITED LAYERS, PLASMA-FACING COMPONENTS, HIGH HEAT-FLUX, CARBON, PARTICLES, EROSION, ITER, CONSEQUENCES, EMISSION
Fusion, Plasma and Space Physics
IdentifiersURN: urn:nbn:se:kth:diva-25575DOI: 10.1088/0031-8949/2009/T138/014025ISI: 000273199200026ScopusID: 2-s2.0-77953881798OAI: oai:DiVA.org:kth-25575DiVA: diva2:371160
12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications Julich, GERMANY, MAY, 2009
QC 201011192012-01-262010-10-272012-11-16Bibliographically approved