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

Materials for future nuclear energy systems must operate under more extreme conditions
than those in current Gen II or Gen III systems. These conditions include higher temperature …

Although FeCrAl ternary alloy is a promising high-temperature material, the structural
features of the FeCrAl remains controversial. To understand the structural features and the …

Sixteen kinds of FeCrAl coatings with different Cr and Al contents were prepared by the
magnetron sputtering method, and the thermal shock resistance and static lead‑bismuth …

Cr-coated Zircaloy-4 samples are prepared by vacuum arc plasma deposition and their
microstructure, corrosion resistance and oxidation behavior are investigated. The as …

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 …

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 …

The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …

In this study, we report a type of ultra oxidation and spallation resistant Y/Hf-doped
AlCoCrFeNi high-entropy alloy (HEA). The alloy exhibits a significantly lower oxidation rate …

The microstructures and mechanical properties of deformed and annealed Nb-containing
FeCrAl alloys were investigated. Fine dispersion of Fe 2 Nb-type Laves phase particles was …