Assessment of materials data for blanket materials within the European contribution to ITER

S. Wikman (Corresponding Author), A. Peacock, O. Zlamal, J. Öijerholm, Seppo Tähtinen, M. Rödig, P. Marmy, O. Gillia, P. Lorenzetto, S. Heikkinen

    Research output: Contribution to journalArticleScientificpeer-review

    6 Citations (Scopus)


    In recent years, material development for ITER blanket components has been fervent; yet, a lack of materials data has been identified by the ITER International Organization (IO) and other ITER parties. Therefore, extensive work on assessment of materials data and qualification of the materials with all the relevant interfaces (joints) has been performed to ensure that requirements are fulfilled for the ITER operational conditions with acceptable margins for the foreseen lifetime of the ITER project. This paper will provide an overview of this qualification program with examples of recent results within the scope of the European contribution of blanket components to ITER. Ongoing actions to achieve a comprehensive understanding of the three main materials, beryllium, CuCrZr and stainless steel grade 316L(N)-IG, and their joints included in the blankets are discussed.
    Original languageEnglish
    Pages (from-to)S414-S419
    JournalJournal of Nuclear Materials
    Issue numberSupplement
    Publication statusPublished - 2013
    MoE publication typeA1 Journal article-refereed
    EventFifteenth International Conference on Fusion Reactor Materials - Charleston, United States
    Duration: 16 Oct 201122 Oct 2011


    Dive into the research topics of 'Assessment of materials data for blanket materials within the European contribution to ITER'. Together they form a unique fingerprint.

    Cite this