The relationship between the microstructural features (such as the solidification cells and
initial dislocation densities) and the tensile properties of alloys additively manufactured (AM) …

FeCrAl alloys have been developed as one of the promising candidates of accident tolerant
fuel (ATF) cladding materials for light water reactor (LWR) to replace zirconium-based alloys …

Two oxide dispersion strengthened (ODS) steels with compositions of 9Cr-ODS (9Cr-ODS)
and 9Cr-3Al-ODS (9Cr-ODS-Al) were fabricated by hot isostatic pressing (HIP). The …

In this work, an integrated approach including experimental examinations and theoretical
modeling was employed to examine the temperature-dependent hardening of structural …

As a candidate material for fuel cladding in fission reactors, the mechanical properties of
ODS-Ferritic/martensitic (F/M) steel should be further improved. Incorporating oxide …

The augmentation of mechanical properties of reduced activation ferritic martensitic steels
through the introduction of creep resistant nano-oxide particles produces a class of oxide …

The collaborative study is focused on the relationship between microstructure and yield
stress for an ODS Fe-9% Cr-based transformable alloy and an ODS Fe-14% Cr-based …

Radiation-induced hardening (RIH) is an important indicator for understanding the radiation-
induced embrittlement and for new materials' selection for the core components in various …

FeCrAl oxide dispersion strengthened (ODS) steel is one of the most promising candidate
cladding materials for Generation IV nuclear reactors due to its superior high temperature …

FeCrAl oxide dispersion strengthened (ODS) steel is regarded as one of the most promising
candidate materials for nuclear fission reactors such as supercritical pressurized water …