Over forty years of in-reactor testing and over thirty years of operating experience in power
reactors have provided a broad understanding of the in-reactor deformation of cold-worked …

Chromium-coated zirconium alloys are being studied as Enhanced Accident Tolerant Fuel
Cladding for Light Water Reactors (LWRs). Those materials are especially studied to …

BWR boiling water reactor CANDU Canadian deuterium uranium reactor CAP cumulative
annealing parameter (£ A) CRNL Chalk River National Laboratory DAD diffusion anisotropy …

Self-diffusion and Al impurity diffusion were studied in the α (hcp) phase of Ti. We used four
Ti materials with different impurity contents, including ultrapure Ti with extremely small …

Reliable experimental diffusion coefficients of 10 key alloying elements in Mg obtained by
the present authors together with experimental data in the literature enabled us to perform a …

The effect of the alloying elements Sn, Fe, Cr, Ni, Nb, and O on hydrogen-containing alpha-
zirconium and zirconium hydrides is investigated using ab initio quantum mechanical …

Abstract Indian Pressurized Heavy Water Reactors (IPHWRs) uses Zr-2.5 Nb alloy pressure
tube (PT) in cold work and stress relieved condition. These PTs are subjected to extreme …

Zirconium alloys used as cladding materials in nuclear reactors can exhibit accelerated
irradiation induced growth, often termed linear growth, after sustained neutron irradiation …

Short-term constant stress creep tests in tension were performed on two zirconium Zr1% Nb
cladding alloys in the form of thin-walled cladding tubes in the temperature range of 623 …

An embedded atom model (EAM) interatomic potential that reproduces room temperature
elastic behavior for α-Zr is developed. At variance with previous potentials from the literature …