Development of divertor tungsten coatings for the JET ITER-like wall

G. F. Matthews (Corresponding Author), P. Coad, H. Greuner, M. Hill, T. Hirai, Jari Likonen, H. Maier, M. Mayer, R. Neu, V. Philipps, R. Pitts, V. Riccardo, JET-EFDA Contributors

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    Abstract

    The main objectives of the JET ITER-like Wall Project are to provide a beryllium main wall and tungsten divertor with at least a 4 year lifetime to allow full evaluation of the materials and related plasma scenarios for ITER. Tungsten coatings will be used over most of the divertor area and this paper describes the latest developments in the coating technology and an analysis of the implications for the coating lifetime and machine operation. Both steady state and transient heat loads are assessed.
    Original languageEnglish
    Pages (from-to)934-937
    Number of pages4
    JournalJournal of Nuclear Materials
    Volume390-391
    DOIs
    Publication statusPublished - 2009
    MoE publication typeA1 Journal article-refereed

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    Keywords

    • tungsten
    • tungsten coating
    • divertor
    • divertor material
    • divertor tiles
    • ITER divertor
    • ITER
    • fusion energy
    • fusion reactors
    • JET divertor
    • plasma
    • plasma transport processes
    • plasma-wall interactions

    Cite this

    Matthews, G. F., Coad, P., Greuner, H., Hill, M., Hirai, T., Likonen, J., Maier, H., Mayer, M., Neu, R., Philipps, V., Pitts, R., Riccardo, V., & JET-EFDA Contributors (2009). Development of divertor tungsten coatings for the JET ITER-like wall. Journal of Nuclear Materials, 390-391, 934-937. https://doi.org/10.1016/j.jnucmat.2009.01.239