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

    13 Citations (Scopus)

    Abstract

    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
    Number of pages6
    JournalNuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms
    Volume268
    Issue number11-12
    DOIs
    Publication statusPublished - 2010
    MoE publication typeA1 Journal article-refereed
    Event19th International Conference on Ion Beam Analysis, IBA 2009 - Cambridge, United Kingdom
    Duration: 7 Sep 200911 Sep 2009

    Fingerprint

    tiles
    Tile
    Ion beams
    erosion
    Erosion
    ion beams
    chambers
    Limiters
    Plasmas
    Plasma interactions
    plasma interactions
    Fueling
    hydrogen isotopes
    refueling
    fusion reactors
    fiber composites
    Fusion reactors
    carbon fibers
    Carbon fibers
    Isotopes

    Keywords

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

    Cite this

    Alves, L. C. ; Alves, E. ; Barradas, N. P. ; Mateus, R. ; Carvalho, P. ; Coad, J. P. ; Widdowson, A. M. ; Likonen, Jari ; Koivuranta, Seppo. / Erosion and re-deposition processes in JET tiles studied with ion beams. In: Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms. 2010 ; Vol. 268, No. 11-12. pp. 1991-1996.
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    abstract = "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.",
    keywords = "Carbon-fibre composites tiles, Fusion reactor materials, Ion beam analysis",
    author = "Alves, {L. C.} and E. Alves and Barradas, {N. P.} and R. Mateus and P. Carvalho and Coad, {J. P.} and Widdowson, {A. M.} and Jari Likonen and Seppo Koivuranta",
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    Erosion and re-deposition processes in JET tiles studied with ion beams. / Alves, L. C. (Corresponding Author); Alves, E.; Barradas, N. P.; Mateus, R.; Carvalho, P.; Coad, J. P.; Widdowson, A. M.; Likonen, Jari; Koivuranta, Seppo.

    In: Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms, Vol. 268, No. 11-12, 2010, p. 1991-1996.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Erosion and re-deposition processes in JET tiles studied with ion beams

    AU - Alves, L. C.

    AU - Alves, E.

    AU - Barradas, N. P.

    AU - Mateus, R.

    AU - Carvalho, P.

    AU - Coad, J. P.

    AU - Widdowson, A. M.

    AU - Likonen, Jari

    AU - Koivuranta, Seppo

    PY - 2010

    Y1 - 2010

    N2 - 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.

    AB - 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.

    KW - Carbon-fibre composites tiles

    KW - Fusion reactor materials

    KW - Ion beam analysis

    U2 - 10.1016/j.nimb.2010.02.115

    DO - 10.1016/j.nimb.2010.02.115

    M3 - Article

    VL - 268

    SP - 1991

    EP - 1996

    JO - Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms

    JF - Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms

    SN - 0168-583X

    IS - 11-12

    ER -