Erosion and re-deposition processes in JET tiles studied with ion beams

L. C. Alves (Corresponding Author), E. Alves, N. P. Barradas, R. Mateus, P. Carvalho, J. P. Coad, A. M. Widdowson, Jari Likonen, Seppo Koivuranta

    Research output: Contribution to journalArticleScientificpeer-review

    17 Citations (Scopus)


    Plasma facing components in fusion reactor chambers will operate under extreme conditions. Among the processes with implications on the material lifetime are erosion and re-deposition due to plasma interactions. This work will address the behaviour of both JET divertor and outer poloidal limiters (OPL) under plasma irradiation. The limiters comprise about 50 pairs of tiles in a poloidal stack, each of which has a plasma facing surface about 25 mm (poloidal) by 350 mm (toroidal) and is about 50 mm thick. The divertor tiles are located at the bottom of the chamber and withstand high fluxes of radiation and heat. Standard carbon-fibre composite (CFC) tiles coated with a thin layer of W overlaid with a 10 μm layer of C were studied with RBS/PIXE to understand the erosion/re-deposition processes occurring in these regions of the reactor chamber. High resolution surface morphology was assessed through SEM with and without tilting of the sample. The retention of hydrogen isotopes in the tiles were studied combining NRA and ERDA techniques – this is mostly 2H from the fuelling gas, but 3H is also present as a result of 2H–2H fusion reactions, and 1H coming from the atmospheric exposure.

    Original languageEnglish
    Pages (from-to)1991-1996
    JournalNuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms
    Issue number11-12
    Publication statusPublished - 2010
    MoE publication typeA1 Journal article-refereed
    Event19th International Conference on Ion Beam Analysis, IBA 2009 - Cambridge, United Kingdom
    Duration: 7 Sept 200911 Sept 2009


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


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