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 …

Zirconium (Zr) hydrides threaten the reliability of fuel assembly and have repeatedly induced
failures in cladding tubes and pressure vessels. Thus, they attract a broad range of research …

To assess the microstructural and mechanical characteristics of hydride blisters formed on
Zircaloy-4 tubes, we employ the electron backscatter diffraction (EBSD) analyses and micro …

Hydride precipitates that develop in Zr after absorbing hydrogen can impart significant
material hardening and embrittlement. Here, we use electrolytic hydrogen charging to …

Nodular corrosion can severely affect the service life of zirconium alloys in water cooled
nuclear reactors. In this study, the susceptibility of pressure tube alloy to undergo nodular …

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 …

Delayed hydride cracking (DHC) is one of the localized forms of hydride embrittlement
caused by hydrogen migration up the tensile stress gradient. In this work, DHC velocity was …

In this work, terminal solid solubility (TSS) of hydrogen for Zr-alloy pressure tube materials
was determined corresponding to end of hydride dissolution (TSSD) and start of hydride …

This study investigates the impact of different processing steps on the crystallographic
texture evolution of αZr and minority phases βZr and ωZr, and intergranular stresses as a …

This paper presents a detailed microstructural characterization by EBSD and TEM
techniques of a hydride blister grown on a Zircaloy-4 plate. The hydrides formed are found to …