Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures

Masayuki Tokitani, Mitsutaka Miyamoto, Suguru Masuzaki, Yuji Hatano, Sun Eui Lee, Yasuhisa Oya, Hironori Kurotaki, Nobuyuki Asakura, Hirofumi Nakamura, Takumi Hayashi, Marek Rubel, Anna Widdowson, Jari Likonen

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    Co-deposited layers on surfaces of bulk tungsten divertor tiles (W lamellae) from the first campaign of JET with the ITER-Like Wall (JET-ILW, 2011–2012) were examined by means of a cross-sectional transmission electron microscope observation. The focus was on geometrical effects in impurity deposition, mainly beryllium (Be), on surfaces located in the poloidal gap separating adjacent lamellae. The study was carried out on the sides (gap surfaces) of two W lamellae from Stack C (located on the outboard part of the horizontal section of the lower divertor), from the region most exposed to the plasma (lamella C23) and in the magnetic shadow of the upstream divertor module (lamella C3). The tile manufacturing process (cold rolling) left shallow grooves, i.e. structures classified as convex (hill) and concave (valley) regions. These regions are decisive for the deposition structure. The main results were: (i) two kinds of impurity deposition features, “homogeneous” and “directional”, have been distinguished; (ii) the directional ones were characterized by nanoscale inclined vertical stripes in the deposition layer; (iii) homogeneous deposition without directional features were in the valley region. The results clearly indicate the impact of the surface finish, even in the tile gaps, on the qualitative and quantitative aspects of deposition.
    Original languageEnglish
    Article number101678
    Pages (from-to)101678
    JournalNuclear Materials and Energy
    Volume39
    DOIs
    Publication statusPublished - 2024
    MoE publication typeA1 Journal article-refereed

    Funding

    This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 \u2014 EUROfusion).

    Keywords

    • Dust
    • Fuel retention
    • Tungsten divertor
    • Deposition layer

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