The characterisation of second phases in the Zr-Nb and Zr-Nb-Sn-Fe alloys: A critical review
The nature and evolution of the Fe environment in Zr-Nb and Zr-Nb-Sn-Fe systems is
essential to alloy performance during corrosion, hardening and irradiation-induced growth …
essential to alloy performance during corrosion, hardening and irradiation-induced growth …
Revealing nanoscale strain mechanisms in ion-irradiated multilayers
Tailoring interfaces is a powerful way of reducing the accumulation of radiation defects.
Understanding strain evolution induced by ion bombardment in nuclear materials with high …
Understanding strain evolution induced by ion bombardment in nuclear materials with high …
Radiation effects in zirconium alloys
F Onimus, S Doriot, JL Béchade - Comprehensive Nuclear …, 2020 - hal-emse.ccsd.cnrs.fr
In this chapter, the effects of neutron irradiation on zirconium alloys are described. Irradiation
effects on the microstructure are first discussed, describing damage creation, point-defect …
effects on the microstructure are first discussed, describing damage creation, point-defect …
[HTML][HTML] Simulation of crystal plasticity in irradiated metals: A case study on Zircaloy-4
A classical crystal plasticity formulation based on dislocation slip was extended to include
the mechanisms of dislocation channelling, with associated strain softening which is …
the mechanisms of dislocation channelling, with associated strain softening which is …
Polycrystalline simulations of in-reactor deformation of recrystallized Zircaloy-4 tubes: Fast Fourier Transform computations and mean-field self-consistent model
F Onimus, L Gelebart, R Brenner - International Journal of Plasticity, 2022 - Elsevier
Fuel cladding and structural components made of zirconium alloys, used in light and heavy
water nuclear reactors, exhibit, during normal operation, significant in-reactor deformation …
water nuclear reactors, exhibit, during normal operation, significant in-reactor deformation …
[HTML][HTML] Two-dimensional vacancy platelets as precursors for basal dislocation loops in hexagonal zirconium
SM Liu, IJ Beyerlein, WZ Han - Nature communications, 2020 - nature.com
Zirconium alloys are widely used structural materials of choice in the nuclear industry due to
their exceptional radiation and corrosion resistance. However long-time exposure to …
their exceptional radiation and corrosion resistance. However long-time exposure to …
Effect of Nb and Fe on damage evolution in a Zr-alloy during proton and neutron irradiation
Detailed analysis was carried out on proton and a neutron irradiated Nb-containing Zr-alloy
to study the evolution of dislocation loop size and densities as well as the formation and …
to study the evolution of dislocation loop size and densities as well as the formation and …
[HTML][HTML] Evolution of dislocation structure in neutron irradiated Zircaloy-2 studied by synchrotron x-ray diffraction peak profile analysis
Dislocation structures in neutron irradiated Zircaloy-2 fuel cladding and channel material
have been characterized by means of high-resolution synchrotron x-ray diffraction combined …
have been characterized by means of high-resolution synchrotron x-ray diffraction combined …
A steady-state irradiation creep and thermal creep model for zirconium alloys
In this work, a mechanistic steady-state creep model is developed to characterize the
macroscopic strain rate of metallic materials affected by irradiation flux, testing temperature …
macroscopic strain rate of metallic materials affected by irradiation flux, testing temperature …
[HTML][HTML] Irradiation damage and hardening in pure Zr and Zr-Nb alloys at 573 K from self-ion irradiation
Zr-ion irradiation was performed on pure Zr, Zr-2.5 Nb, and Zr-5Nb to a dose of 0.5 or 5 dpa
at 573 K. The irradiation induced defects, alloying element redistribution, precipitation, and …
at 573 K. The irradiation induced defects, alloying element redistribution, precipitation, and …