Following the severe accident at the Fukushima Daiichi nuclear power plant in 2011,
recrystallized FeCrAl-ODS claddings have been developed in Japan as an accident-tolerant …

Abstract Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated
for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys …

Abstract The Fe–Cr–Al alloy system has the potential to form an important class of enhanced
accident-tolerant cladding materials in the nuclear power industry owing to the alloy …

After the Fukushima nuclear accident, the development of new accident-tolerant fuel
cladding materials has become a research hotspot around the world. Due to its outstanding …

FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power
applications including accident tolerant fuel cladding, structural components for fast fission …

The oxidation behavior of CrAl coatings with three representative compositions deposited on
Zircaloy-4 in 1200° C steam environment has been studied. The Cr 0.90 Al 0.10 coating …

Post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF)
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …

Abstract Iron–Chromium–Aluminium (Fe–Cr–Al) alloys have been widely investigated as
candidate materials for various nuclear applications. Albeit the excellent corrosion …

FeCrAl alloys are promising candidates for next generation nuclear fuel cladding
applications due to their high resistance to hydrothermal corrosion, high temperature steam …

Segregation of alloying elements to a prismatic dislocation loop under irradiation is an
important phenomenon in understanding the role of loops in radiation effects in alloys. In this …