Surface composition and morphology changes of JET tiles under plasma interactions

JET-EFDA collaborators

    Research output: Contribution to journalArticleScientificpeer-review

    4 Citations (Scopus)

    Abstract

    Plasma interactions with the main chamber of magnetic fusion devices result in net erosion from some areas and net deposition at other locations. However, high energy particle irradiation means that there are continuous erosion and re-deposition processes involved, creating new surface structures. Although the net deposition can be readily assessed, net erosion and material mixing is difficult to determine. In 2005 marker tiles were mounted in the JET vessel which have a thin tungsten (W) layer deposited on the CFC substrate with a ∼10 μm carbon layer on top. This layered structure was designed to determine the areas where some erosion had occurred during JET plasma operations, when the tiles were removed for analysis in 2007.

    This paper describes the results from a set of tiles mounted in a poloidal limiter (in Octant 8) at the outer wall of the main chamber; a comparison is made between the data from tiles near the top, middle and bottom of the limiter. A set of ion beam techniques together with electron microscopy were used to provide a detailed analysis of the tiles. In general, since plasma interaction is strongest near the centre of the limiter where the tile is closest to the boundary of the confined plasma, erosion dominated on the central tiles, with deposition further from the plasma boundary. Also the amount of retained deuterium is higher in the tiles located in the upper and lower regions of the plasma chamber.
    Original languageEnglish
    Pages (from-to)2557-2560
    Number of pages4
    JournalFusion Engineering and Design
    Volume86
    Issue number9-11
    DOIs
    Publication statusPublished - 2011
    MoE publication typeA1 Journal article-refereed
    Event26th Symposium of Fusion Technology, SOFT-26 - Porto, Portugal
    Duration: 27 Sep 20101 Oct 2010
    Conference number: 26

    Keywords

    • Ion beam analysis
    • Carbon fibre composites tiles
    • Fusion reactor materials

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