Nucleation and formation of hydride precipitates in zirconium alloys have been an important
factor in limiting the lifetime of nuclear fuel cladding for over 50 years. This review provides a …

The zirconium alloys used in nuclear industry include mainly Zr–Sn and Zr–Nb alloys of
different chemical composition, microstructure and susceptibility to both hydrogen …

Hydrogen embrittlement is an important degradation mechanism affecting the lifetime of
engineering components. The diffusion of hydrogen atoms into the metal lattice can be …

A theoretical understanding of the intergranular δ-hydrides is still lacking, although hydride-
related degradation of the mechanical properties of zirconium alloys has been studied for …

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 …

The usage and long-term storage of nuclear fuel cladding motivate efforts to understand the
effect of external stress on hydride precipitation. Here, by using in situ bending device in …

The alloying effects of Sn, Nb, Cr, and Mo on zirconium alloys were elucidated and
compared. Electron backscatter diffraction, transmission electron microscopy, tensile test …

Cold-worked and stress relieved (CWSR) zircaloy-4 sheet-samples were charged with 45–
247wt. ppm of hydrogen using an electrolytic technique. Morphology and orientation of …

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

Developments in crystallographic texture and in microstructure were characterized during
the fabrication steps of Zircaloy-4 fuel tube. Textural developments were generalized in …