Analysis of fuel retention in plasma-facing components from controlled fusion devices

M. Rubel (Corresponding Author), J. P. Coad, Jari Likonen, V. Philipps, JET-EFDA Contributors

    Research output: Contribution to journalArticleScientificpeer-review

    15 Citations (Scopus)

    Abstract

    First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.
    Original languageEnglish
    Pages (from-to)711-717
    Number of pages7
    JournalNuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms
    Volume267
    Issue number4
    DOIs
    Publication statusPublished - 2009
    MoE publication typeA1 Journal article-refereed
    Event17th International Workshop on Inelastic Ion-Surface Collisions - Porquerolles, France
    Duration: 21 Sep 200826 Sep 2008

    Fingerprint

    controlled fusion
    Facings
    Fusion reactions
    Plasmas
    Surface analysis
    Beam plasma interactions
    high temperature plasmas
    Ion beams
    erosion
    Erosion
    ion beams
    interactions

    Keywords

    • Controlled thermonuclear fusion
    • Wall materials
    • Retention
    • Deuterium
    • Tokamak

    Cite this

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    title = "Analysis of fuel retention in plasma-facing components from controlled fusion devices",
    abstract = "First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.",
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    author = "M. Rubel and Coad, {J. P.} and Jari Likonen and V. Philipps and {JET-EFDA Contributors}",
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    Analysis of fuel retention in plasma-facing components from controlled fusion devices. / Rubel, M. (Corresponding Author); Coad, J. P.; Likonen, Jari; Philipps, V.; JET-EFDA Contributors.

    In: Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms, Vol. 267, No. 4, 2009, p. 711-717.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Analysis of fuel retention in plasma-facing components from controlled fusion devices

    AU - Rubel, M.

    AU - Coad, J. P.

    AU - Likonen, Jari

    AU - Philipps, V.

    AU - JET-EFDA Contributors, null

    PY - 2009

    Y1 - 2009

    N2 - First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.

    AB - First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.

    KW - Controlled thermonuclear fusion

    KW - Wall materials

    KW - Retention

    KW - Deuterium

    KW - Tokamak

    U2 - 10.1016/j.nimb.2008.11.035

    DO - 10.1016/j.nimb.2008.11.035

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    SP - 711

    EP - 717

    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

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    ER -