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).
|Journal||Microscopy and Microanalysis|
|Issue number||Supl. S2|
|State||Published - Dec 2012|
|Event||Microscopy and Microanalysis 2012 - Microscopy Society of America, Microanalysis Society, International Metallographic Society., Phoenix|
Duration: 29 Jul 2012 → 2 Aug 2013