Abstract The effects of 5 MeV Fe 2+ ion irradiation at 300° C on the microstructure evolution
and deformation behavior of a FeCrAl C26M alloy are presented. It has been found that …

Abstract Model FeCrAl alloys of Fe-10% Cr-5% Al, Fe-12% Cr-4.5% Al, Fe-15% Cr-4% Al,
and Fe-18% Cr-3% Al (in wt%) were irradiated with 1 MeV Kr++ ions in-situ with …

FeCrAl alloys are an attractive class of materials for nuclear power applications because of
their increased environmental compatibility compared with more traditional nuclear …

The deformed microstructures of both irradiated and unirradiated Fe-9% Cr (Fe-9Cr) uniaxial
tensile specimens have been examined to identify controlling mechanisms. Deformation …

FeCrAl ferritic alloys are excellent cladding candidates for accident tolerant fuel systems due
to their high resistance to oxidation as a result of formation of a protective Al 2 O 3 scale at …

FeCrAl alloys are candidates for accident tolerant fuel cladding of light water reactors. In this
work, a microstructure-and temperature-dependent crystal plasticity model is employed to …

Nano indentation analysis and transmission electron microscopy observation were
performed to investigate a microstructural evolution and its influence on the hardening …

Abstract Iron-chromium-aluminum (FeCrAl) alloys with different content of niobium (Nb)—0,
0.4 wt%, 0.8 wt%, and 1.2 wt%—were designed and prepared. All samples were then …

It is generally accepted that the microstructure of ion-irradiated Fe-based alloys does not
only depend on the local level of displacement damage and the initial microstructure. Other …

The attractive mechanical properties and superior resistance to void-swelling make
ferritic/martensitic alloys a promising structural material for advanced nuclear reactors …