Overview of recent European materials R&D activities related to ITER

A.T. Peacock (Corresponding Author), V. Barabash, W. Dänner, M. Rödig, P. Lorenzetto, P. Marmy, M. Merola, B.N. Singh, Seppo Tähtinen, J. van der Laan, C.H. Wu

    Research output: Contribution to journalArticleScientificpeer-review

    30 Citations (Scopus)


    An overview is given of the wide range of activities contained within recent R&D being performed within Europe on In-vessel materials for structural, heat sink and plasma facing purposes for ITER. The effect of creep-fatigue interaction on the fatigue life of CuCrZr and the effects of irradiation on over-aged CuCrZr are given. In addition the lifetime of ITER components has been further investigated by the performance of in situ experiments with both neutrons and high-energy protons. The effect of hydrogen on the crack initiation fracture toughness of Ti is reported at a range of irradiation temperatures. The irradiation induced stress relaxation of Alloy 718 used for bolting applications is being studied and initial results will be described. Work in the area of plasma facing materials and re-welding issues will also be presented.
    Original languageEnglish
    Pages (from-to)173-177
    Number of pages5
    JournalJournal of Nuclear Materials
    Publication statusPublished - 2004
    MoE publication typeA1 Journal article-refereed
    Event11th International Conference on Fusion Reactor Materials (ICFRM-11) - Kyoto, Japan
    Duration: 7 Dec 200312 Dec 2003


    • ITER
    • fusion energy
    • fusion reactors
    • fatigue (materials)
    • materials
    • fatique
    • crack initiation
    • crack propagation


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