Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall

Y. Zhou, H. Bergsåker, I. Bykov, P. Petersson, G. Possnert, J. Likonen, J. Pettersson, S. Koivuranta, A. Widdowson

    Research output: Contribution to journalArticleScientificpeer-review

    3 Citations (Scopus)

    Abstract

    In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.
    Original languageEnglish
    Pages (from-to)412-417
    Number of pages6
    JournalNuclear Materials and Energy
    Volume12
    Early online date2017
    DOIs
    Publication statusPublished - 1 Aug 2017
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Microanalysis
    microanalysis
    surface roughness effects
    impurities
    Impurities
    fiber composites
    Beryllium
    tiles
    beryllium
    carbon fibers
    Tungsten
    Deuterium
    closures
    Tile
    deuterium
    flat surfaces
    tungsten
    cracks
    arcs
    Ion beams

    Keywords

    • carbon
    • carbon fibers
    • fusion reactor divertors
    • Ion beams
    • surface roughness
    • deposited layer
    • elemental maps
    • flat surfaces
    • horizontal surfaces
    • Ion beam analysis
    • plasma operations
    • surface roughness effects
    • tungsten coated carbon

    Cite this

    Zhou, Y. ; Bergsåker, H. ; Bykov, I. ; Petersson, P. ; Possnert, G. ; Likonen, J. ; Pettersson, J. ; Koivuranta, S. ; Widdowson, A. / Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall. In: Nuclear Materials and Energy. 2017 ; Vol. 12. pp. 412-417.
    @article{271857e86a634978a4ef94874292210c,
    title = "Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall",
    abstract = "In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.",
    keywords = "carbon, carbon fibers, fusion reactor divertors, Ion beams, surface roughness, deposited layer, elemental maps, flat surfaces, horizontal surfaces, Ion beam analysis, plasma operations, surface roughness effects, tungsten coated carbon",
    author = "Y. Zhou and H. Bergs{\aa}ker and I. Bykov and P. Petersson and G. Possnert and J. Likonen and J. Pettersson and S. Koivuranta and A. Widdowson",
    year = "2017",
    month = "8",
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    doi = "10.1016/j.nme.2017.02.015",
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    Zhou, Y, Bergsåker, H, Bykov, I, Petersson, P, Possnert, G, Likonen, J, Pettersson, J, Koivuranta, S & Widdowson, A 2017, 'Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall', Nuclear Materials and Energy, vol. 12, pp. 412-417. https://doi.org/10.1016/j.nme.2017.02.015

    Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall. / Zhou, Y.; Bergsåker, H.; Bykov, I.; Petersson, P.; Possnert, G.; Likonen, J.; Pettersson, J.; Koivuranta, S.; Widdowson, A.

    In: Nuclear Materials and Energy, Vol. 12, 01.08.2017, p. 412-417.

    Research output: Contribution to journalArticleScientificpeer-review

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    AU - Zhou, Y.

    AU - Bergsåker, H.

    AU - Bykov, I.

    AU - Petersson, P.

    AU - Possnert, G.

    AU - Likonen, J.

    AU - Pettersson, J.

    AU - Koivuranta, S.

    AU - Widdowson, A.

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    Y1 - 2017/8/1

    N2 - In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.

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    KW - carbon fibers

    KW - fusion reactor divertors

    KW - Ion beams

    KW - surface roughness

    KW - deposited layer

    KW - elemental maps

    KW - flat surfaces

    KW - horizontal surfaces

    KW - Ion beam analysis

    KW - plasma operations

    KW - surface roughness effects

    KW - tungsten coated carbon

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    M3 - Article

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    EP - 417

    JO - Nuclear Materials and Energy

    JF - Nuclear Materials and Energy

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