In the spent fuel storage phase, nuclear fuel cladding is subjected to increased
embrittlement owing to a large amount of hydride precipitation. This study compares the …

This paper presents observations of in situ heating and cooling cycles using synchrotron X-
ray diffraction carried out on Zircaloy-4 plates charged to different levels of hydrogen …

We report a phase-field model for simulating metal hydride formation involving large volume
expansion in single-and polycrystals. As an example, we consider δ-hydride formation in α …

Zirconium (Zr) alloys are the primary structural materials of most water reactors. Creep is
considered to be one of the important degradation mechanisms of Zr alloys during reactor …

Stable and high surface area zirconium oxide nanoparticles have been synthesised by
means of the hydrothermal method. The Brunauer–Emmett–Teller results show that a high …

The difficulty in characterizing mesoscale hydrides in the highly deformed submicron (< 1 μ
m) scale grain size of the reactor-grade stress-relief annealed (SRA) zirconium-based alloy …

Hydride reorientation is a major degradation mechanism of zirconium-based alloys used for
nuclear fuel cladding tubes. A previous commonly used thermodynamic model has limited …

This article investigated the impact of intergranular hydride precipitation on the mechanical
behavior of zirconium (Zr) bi-crystals using molecular dynamics (MD)-based simulations …

High-energy synchrotron X-ray diffraction was used to investigate the isothermal
precipitation of δ-hydride platelets in Zircaloy-4 at a range of temperatures relevant to …

Delayed hydride cracking (DHC) threatens the safety and integrity of Zircaloy components.
The typical feature of DHC is presented as the intermittent fracture with the striations on the …