Abstract
Ferritic-martensitic (F/M) alloys are expected to play an important role as cladding or structural components in Generation IV and other advanced nuclear systems operating in the temperature range 350-700 °C and to doses up to 200 displacements per atom (dpa). Oxide dispersion strengthened (ODS) F/M steels have been developed to operate at higher temperatures than traditional F/M steels. These steels contain nanometer-sized Y-Ti-O nanoclusters for additional strengthening. A proton irradiation to 1 dpa at 525 °C has been performed on a 9Cr ODS steel to determine the nanocluster stability at low dose. The evolution of the nanocluster population and the composition at the nanocluster-matrix interface were studied using electron microscopy and atom probe tomography. The data from this study are contrasted to those from a previous study on heavy-ion irradiated 9Cr ODS steel.
Original language | English |
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Pages (from-to) | 2-9 |
Number of pages | 8 |
Journal | Journal of Nuclear Materials |
Volume | 407 |
Issue number | 1 |
DOIs | |
State | Published - Dec 1 2010 |
Funding
STEM/EDS, EFTEM and APT research at Oak Ridge National Laboratory was sponsored by the Division of Materials Sciences and Engineering, Office of Basic Energy Sciences, by the Advanced Fuel Cycle Initiative, Office of Nuclear Energy, Science and Technology, and at the SHaRE User Facility sponsored by the Division of Scientific User Facilities, Office of Basic Energy Sciences, US Department of Energy. The ODS sample material was generously provided by the Japan Atomic Energy Agency.