The motivation for transitioning away from zirconium-based fuel cladding in light water
reactors to significantly more oxidation-resistant materials, thereby enhancing safety …

Abstract Zirconium-based (Zr-based) alloys have been widely used as materials for the key
components in light water reactors (LWRs), such as fuel claddings which suffer from …

BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …

The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …

The intricate balance between reactor economics and safety necessitates the emergence of
new and advanced nuclear systems and, very importantly, advanced materials, which can …

Abstract Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel
cladding for increased accident tolerance. An analysis of the response of FeCrAl under …

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 …

A ZrO 2/FeCrAl bilayer coating was prepared on Zr-4 alloy. Plasma electrolytic oxidation
(PEO) was used to synthesize the ZrO 2 buffer layer and magnetron sputtering was used to …

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 CrAl coating of 13 µm thick on Zr–1 Nb alloy prepared by filtered cathodic vacuum arc
deposition with Cr70Al30 target exhibited excellent steam oxidation resistance below 1200° …