Initial APT Analysis of Irradiated MA957

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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
Publication statusPublished - Dec 2012
EventMicroscopy and Microanalysis 2012 - Microscopy Society of America, Microanalysis Society, International Metallographic Society., Phoenix, United States
Duration: 29 Jul 20122 Aug 2013


  • APT, ODS, MA957, MOTA

ID: 268630