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 …

Zirconium alloys are widely used for fuel cladding and in pressure tubes, fuel channels
(boxes), and fuel spacer grids in almost all water-cooled reactors: light water reactors such …

A detailed characterization of nanostructured thin zirconium oxide films formed during
aqueous corrosion of a nuclear-grade zirconium alloy (Zircaloy-4) has been carried out by …

The desire to improve the corrosion resistance of Zr cladding material for high burn-up has
resulted in a general trend among fuel manufacturers to develop alloys with reduced levels …

Tailoring microstructure and microchemistry by altering elemental compositions and
thermomechanical treatment parameters enables superior corrosion performance in …

Displacive transformations have been widely reported in metals, alloys and ceramics, but
rarely reported to be important in the aqueous corrosion of alloys. We report here our …

Corrosion is a key limiting factor in the degradation of zirconium alloys in light water
reactors. Developing a mechanistic understanding of the corrosion process offers a route …

The development of oxide texture and microstructure formed on two zirconium alloys with
differing Sn contents (Zr–1Nb–1Sn–0.1 Fe, ie ZIRLO™ and Zr–1.0 Nb–0.1 Fe) has been …

A review of the data available in the literature on the residual stress determination in zirconia
scales has been undertaken. Deflexion method and curvature measurement as well as …