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FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding applications in light water reactors owing to their superior hightemperature oxidation and corrosion resistance compared to the Zr-based alloys currently employed. However, their performance could be limited by precipitation of a Cr-rich α phase that tends to embrittle high-Cr ferritic Fe-based alloys. In this study, four FeCrAl model alloys with 1018 at.% Cr and 5.89.3 at.% Al were neutron-irradiated to nominal damage doses up to 7.0 displacements per atom at a target temperature of 320. Small angle

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