The fuel channels and fuel assemblies of all conventional nuclear reactors that generate
power from the fission of uranium by thermal neutrons are made from zirconium alloys …

The microstructure developed in Zr alloys during irradiation has proven to be increasingly
complicated as specimens of varying composition and thermo-mechanical history have …

Over forty years of in-reactor testing and over thirty years of operating experience in power
reactors have provided a broad understanding of the in-reactor deformation of cold-worked …

Irradiation growth is thought to occur when there is an anisotropic distribution of sinks
receiving a net flux of vacancies and this anisotropy is different from that of the distribution of …

A summary of known experimental results on in-reactor creep and irradiation growth is
presented in terms of behavioural trends. The information is drawn primarily from …

Microstructural changes occurring during the fabrication of Zr-2.5 pct Nb alloy pressure
tubes by a modified route, involving hot extrusion followed by two pilgering operations with …

An approach to transform and accelerate nuclear fuel development and qualification is
outlined. The approach exploits advanced modeling and simulation at the outset to inform …

In situ neutron diffraction has been carried out on fast neutron irradiated Zr–2.5 Nb pressure
tube and non-irradiated Zr–2.5 Nb pressure tube samples, with tensile deformation applied …

Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as
fuel cladding and guide tubes because they have excellent corrosion-and radiation-resistant …

Pressure tubes were initially made of Zircaloy-2 but for Pickering Unit 3 and all subsequent
power reactors, pressure tubes have been made from Zr-2, 5 wt% Nb, The current tubes …