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Interaction of candidate plasma facing materials with tokamak plasma in COMPASS
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SYSNO ASEP 0476111 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title Interaction of candidate plasma facing materials with tokamak plasma in COMPASS Author(s) Matějíček, Jiří (UFP-V) RID, ORCID
Weinzettl, Vladimír (UFP-V) RID, ORCID
Macková, Anna (UJF-V) RID, ORCID, SAI
Malinský, Petr (UJF-V) RID, ORCID, SAI
Havránek, Vladimír (UJF-V) RID, SAI, ORCID
Naydenkova, Diana (UFP-V) RID, ORCID
Klevarová, Veronika (UFP-V)
Petersson, P. (SE)
Gasior, P. (PL)
Hakola, A. (FI)
Rubel, M. (SE)
Fortuna, E. (PL)
Kolehmainen, J. (FI)
Tervakangas, S. (FI)Source Title Journal of Nuclear Materials. - : Elsevier - ISSN 0022-3115
Roč. 493, September (2017), s. 102-119Number of pages 18 s. Publication form Print - P Action International Conference on Plasma-Facing Materials and Components for Fusion Applications/15./ Event date 18.05.2015 - 22.05.2015 VEvent location Aix-en-Provence Country FR - France Event type WRD Language eng - English Country NL - Netherlands Keywords erosion ; COMPASS tokamak ; plasma-material interaction ; ion beam analysis Subject RIV JF - Nuclear Energetics OECD category Nuclear related engineering Subject RIV - cooperation Nuclear Physics Institute - Nuclear Energetics R&D Projects GA14-12837S GA ČR - Czech Science Foundation (CSF) GA15-10723S GA ČR - Czech Science Foundation (CSF) LM2015045 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) LM2015056 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) Institutional support UFP-V - RVO:61389021 ; UJF-V - RVO:61389005 UT WOS 000408044000013 EID SCOPUS 85020041707 DOI 10.1016/j.jnucmat.2017.06.009 Annotation The interaction of tokamak plasma with several materials considered for the plasma facing components of future fusion devices was studied in a small-size COMPASS tokamak. These included mainly tungsten as the prime candidate and chromium steel as an alternative whose suitability was to be assessed. For the experiments, thin coatings of tungsten, P92 steel and nickel on graphite substrates were prepared by arcdischarge sputtering. The samples were exposed to hydrogen and deuterium plasma discharges in the COMPASS tokamak in two modes: a) short exposure (several discharges) on a manipulator in the proximity of the separatrix, close to the central column, and b) long exposure (several months) at the
central column, aligned with the other graphite tiles. During the discharges, standard plasma diagnostics were used and a local emission of spectral lines in the visible near ultraviolet regions, corresponding to the material erosion, was monitored. Before and after the plasma exposures, the sample surfaces were observed using scanning electron microscopy, the coatings thickness was measured using Rutherford backscattering spectroscopy, and the concentration profiles of hydrogen and deuterium were measured by elastic recoil detection analysis. The uniformity of the coatings and their thickness was verified before the exposure. After the exposure, no reduction of the thickness was observed, indicating the absence of ‘global’ erosion. Erosion was observed only in isolated spots, and attributed to unipolar arcing. Slightly larger erosion was found on
the steel coatings compared to the tungsten ones. Incorporation of deuterium in a thin surface layer was observed, in dependence on the exposure mode. Additionally, boron enrichment of the long-exposure samples was observed, as a result of the tokamak chamber boronizationWorkplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2018
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