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Zirconium Alloys in Nuclear Applications
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In situ XRD analysis of the oxide layers formed by oxidation at 743 K on Zircaloy 4 and Zr–1NbO
Abstract Two alloys, having different oxidation behaviour (Zy4 and Zr–1NbO), have been investigated during oxidation at high temperature (743 K) and low oxygen pressure (10 kPa) by in situ X-rayExpand
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Precipitate evolution in the Zircaloy-4 oxide layer
A study by transmission electron microscopy has been made of the incorporation and oxidation of intermetallic precipitates Zr(Cr,Fe)2 into the uniform oxide layer of Zircaloy-4. Oxide thicknesses ofExpand
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A thermodynamic database for zirconium alloys
Abstract A thermodynamic database, Zircobase, was developed for zirconium alloys for use in the nuclear industry. Two examples of the assessments concerning the Sn–Zr and H–Zr systems are given. TheExpand
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Oxidation behaviour of zirconium alloys and their precipitates – A mechanistic study
Abstract The precipitate oxidation behaviour of binary zirconium alloys containing 1 wt.% Fe, Ni, Cr or 0.6 wt.% Nb was characterised in TEM on FIB prepared transverse sections of the oxide andExpand
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Direct evidence of nanometric invasionlike grain boundary penetration in the A(1)/Ga system.
We report the first in situ results of deformation during grain boundary penetration in the A(1)/Ga system, obtained with a novel, nondestructive hard x-ray synchrotron projection microscopyExpand
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Microstructural study of oxide layers formed on Zircaloy-4 in autoclave and in reactor part 11: Impact of the chemical evolution of intermetallic precipitates on their zirconia environment
Abstract A cause and effect relationship is likely established between the microstructural changes in zirconium alloys under irradiation and the acceleration of their oxidation process. In order toExpand
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Experimental study and numerical modelling of the irradiation damage recovery in zirconium alloys
Neutron irradiation damage in zirconium alloys used as fuel cladding tubes for Pressurized Water Reactors in the nuclear industry consists mainly in a high density of small prismatic dislocationExpand
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Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
TEM investigations in Zr-Fe and Zr-Fe-Ni, Zr-Ni-Cr and Zr-Cr-Fe systems were performed to assess the second particles present in these alloys, either in quasi equilibrium conditions, or afterExpand
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