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 …

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 …

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 …

Precipitation morphology and habit planes of the δ-phase Zr hydrides, which were
precipitated within the a-phase matrix grains and along the grain boundaries of …

This research describes the possibility of ultra-high dose deep titanium ion implantation for
surface modification of zirconium alloy Zr-1Nb. The developed method based on repetitively …

Abstract Samples of annealed Zr-1Nb alloy were deformed under uniaxial compression in
the temperature range of 600–900° C and the strain rate range of 10− 3 to 1s− 1. The strain …

The influence of chromium coating on hydrogenation behavior of laser beam welds (LBW) of
E110 zirconium alloy was studied at 360–900° C and hydrogen pressure of 2 bar. The …

We present a fast and accurate method for predicting the thermodynamics of hydrogen
solubility and trapping in alloys, which is two orders of magnitude faster than conventional …

This work presents a detailed microstructure and texture study of various hydrided Zircaloy-4
materials by neutron diffraction and microscopy. The results show that the precipitated δ …

Hot deformation behavior of β-quenched Zr–1Nb was studied by constructing a processing
map in the temperature range of 600–950° C and strain rate range 0.002–10 s− 1. The …