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 …

Hydrogen in excess of the terminal solid solubility precipitates out as a brittle hydride phase
in zirconium alloys. The hydrides acquire platelet shaped morphology due to their …

High-resolution electron backscatter diffraction (HR-EBSD) can provide an estimate of
elastic strains at a microscopic scale. Due to the need for high-quality Kikuchi patterns, HR …

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 …

Plasma electrolytic oxidation (PEO) process was employed in a galvanostatic regime on Zr-
2.5 Nb alloy in NaAlO 2 aqueous electrolyte solutions within a concentration gradient of 5 …

The fracture behavior of Zr-2.5 Nb pressure tube (PT) material containing radial hydrides
with hydrogen concentrations between 30 and 300wppm was evaluated between 25 and …

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 …

Delayed hydride cracking (DHC) is a potential failure mechanism of Zr-2.5 Nb alloy pressure
tubes, employed in heavy-water reactors. This study focused on understanding the DHC …

Hydrogen embrittlement, also known as hydrogen-induced cracking, is a longstanding
concern for zirconium (Zr) and its alloys. The affinity for hydrogen in zirconium results in the …