UO 2 has a long history being used as a nuclear fuel. However, its low thermal conductivity
has become one of the major concerns limiting nuclear reactor performance and safety …

High-entropy materials represent the state-of-the-art on the alloy design strategy for future
applications in extreme environments. Recent data indicates that high-entropy alloys (HEAs) …

Abstract The United States Department of Energy Advanced Fuels Campaign in
collaboration with industry is working to develop enhanced accident tolerant fuels for light …

In this work, we present a model of fission gas behavior in U 3 Si 2 under light water reactor
(LWR) conditions for application in engineering fuel performance codes. The model includes …

U 3 Si 2 is a potential accident-tolerant fuel that shows promise due to its high thermal
conductivity and higher uranium density relative to UO 2. However, its swelling and fission …

Finely dispersed two phase microstructures resulting from a spinodal decomposition are of
interest as they are associated with enhanced mechanical properties and excessive …

U-50wt% Zr is a candidate metallic nuclear fuel with potential application in light water
reactors due to its excellent thermal properties and high radiation tolerance. The Zr-rich UZr …

In recent years, U3Si2 has been proposed as an alternative nuclear fuel material to uranium
dioxide (UO2) because of its intrinsically high uranium density and thermal conductivity …

This paper investigated the formation of bubbles and precipitates and the hardening effects
in V–4Cr–4Ti alloy after irradiation of He and H ions and post-irradiation annealing …

We have developed a mesoscale model to calculate the degradation of the effective thermal
conductivity in irradiated U-Mo alloys caused by the fission-induced gas bubbles and …