Initial APT Analysis of Irradiated MA957

N. Bailey, P. Hosemann, Erich Stergar, M. Toloczko, Serguei Gavrilov

    Research outputpeer-review


    Due, in part, to the fine dispersion of Y-Ti-O enriched particles throughout the material, oxide dispersion strengthened (ODS) ferritic steels are attractive structural materials for radiation environments in nuclear reactor systems because of their potential swelling and helium embrittlement resistance [1,2]. Summarized here are some early atom probe tomography (APT) investigations on the oxide particle morphology and chromium cluster formation in the ODS steel MA957 that underwent irradiation in the Fast Flux Test Facility-Materials Open Test Assembly (FFTF-MOTA) for the Liquid Metal Fast Breeder Program (LMFBR).
    Original languageEnglish
    Pages (from-to)1418-1419
    JournalMicroscopy and Microanalysis
    Issue numberSupl. S2
    StatePublished - Dec 2012
    EventMicroscopy and Microanalysis 2012 - Microscopy Society of America, Microanalysis Society, International Metallographic Society., Phoenix
    Duration: 29 Jul 20122 Aug 2013

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