Fabrication and mechanical properties of oxide dispersion strengthening ferritic alloy canning tubes for fast reactor fuel pins.

J. J. Huet, L. Coheur, A. De Bremaecker, L. De Wilde, Jan Gedopt, W. Hendrix, W. Vandermeulen

    Research outputpeer-review

    Abstract

    Ferritic steels are interesting for fast reactor core application because of the absence of swelling. As canning material, because of the higher temperature involved, new ferritic steels with oxide dispersion strengthening were developed. Fabrication methods are given and their mechanical irradiation and sodium compatibility properties are reviewed.

    Original languageEnglish
    Pages (from-to)215-219
    Number of pages5
    JournalNuclear Technology
    Volume70
    Issue number2
    DOIs
    StatePublished - 1985

    ASJC Scopus subject areas

    • Nuclear and High Energy Physics
    • Nuclear Energy and Engineering
    • Condensed Matter Physics

    Cite this