During operation, nuclear fuel rods are immersed in the primary water, causing waterside
corrosion and consequent hydrogen ingress. In this review, the mechanisms of corrosion …

Zirconium-based alloys (Zr alloys) are key materials in the nuclear industry due to their
thermal stability, mechanical durability, and low thermal neutron cross section. However …

We investigate the electronic and thermodynamic properties of Zr and its oxides from first
principles to elucidate phase stability in the Zr-O system. Hexagonally close-packed Zr is …

Aqueous corrosion and hydrogenation have become major limiting factors to the use of
zirconium alloys as fuel cladding and assembly components in water-cooled nuclear …

A detailed study of alloying element distributions in the metal and oxygen rich regions of
corroded Zr alloys and of the phases formed ahead of the oxide front was conducted using …

This work describes the development of transparent high-strength Yttria-Stabilized Zirconia
(YSZ) ceramics with ultra-fine grain size utilizing conventional pressure-less densification …

Zirconium‐based alloys are used in water‐cooled nuclear reactors for both nuclear fuel
cladding and structural components. Under this harsh environment, the main factor limiting …

Here we report a methodology combining TEM, STEM, Transmission-EBSD and EELS to
analyse the structural and chemical properties of the metal–oxide interface of corroded Zr …

Flash sintering of cubic yttria-stabilized zirconia has been studied via in situ energy
dispersive diffraction. A secondary rocksalt-phase zirconium monoxide was observed …

Pressurised and boiling water reactors contain zirconium alloys, which are used as nuclear
fuel cladding. Oxidation of these alloys, and the associated hydrogen pick-up, is a limiting …