作者: A.G. Certain , K.G. Field , T.R. Allen , M.K. Miller , J. Bentley
DOI: 10.1016/J.JNUCMAT.2010.07.002
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摘要: 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 the temperature range 350–700 °C doses up 200 displacements per atom (dpa). Oxide dispersion strengthened (ODS) F/M steels have been developed operate at higher temperatures than traditional steels. These contain nanometer-sized Y–Ti–O nanoclusters for additional strengthening. A proton irradiation 1 dpa 525 °C has performed on a 9Cr ODS steel determine nanocluster stability low dose. The evolution of population composition nanocluster–matrix interface were studied using electron microscopy probe tomography. data from this study contrasted those previous heavy-ion irradiated steel.