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- Publications
- Influence
Zirconium Alloys in Nuclear Applications
- C. Lemaignan, A. Motta
- Materials Science
- 15 September 2006
In situ XRD analysis of the oxide layers formed by oxidation at 743 K on Zircaloy 4 and Zr–1NbO
- N. Pétigny, P. Barbéris, C. Lemaignan, C. Valot, M. Lallemant
- Materials Science
- 1 August 2000
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-ray… Expand
Precipitate evolution in the Zircaloy-4 oxide layer
- D. Pêcheur, F. Lefebvre, A. Motta, C. Lemaignan, J. Wadier
- Chemistry
- 1 August 1992
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 of… Expand
A thermodynamic database for zirconium alloys
- N. Dupin, I. Ansara, C. Servant, C. Toffolon, C. Lemaignan, J. Brachet
- Chemistry
- 1 November 1999
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. The… Expand
Oxidation behaviour of zirconium alloys and their precipitates – A mechanistic study
- C. Proff, S. Abolhassani, C. Lemaignan
- Materials Science
- 2013
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 and… Expand
Direct evidence of nanometric invasionlike grain boundary penetration in the A(1)/Ga system.
- E. Pereiro-López, W. Ludwig, D. Bellet, P. Cloetens, C. Lemaignan
- Materials Science, Medicine
- Physical review letters
- 14 November 2005
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 microscopy… Expand
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
- X. Iltis, F. Lefebvre, C. Lemaignan
- Chemistry
- 1 August 1995
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 to… Expand
Experimental study and numerical modelling of the irradiation damage recovery in zirconium alloys
- J. Ribis, F. Onimus, +4 authors C. Lemaignan
- Chemistry
- 1 August 2010
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 dislocation… Expand
Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
- P. Barbéris, N. Dupin, C. Lemaignan, A. Pasturel, J. Grange
- Materials Science
- 2 May 2005
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 after… Expand
Role of the Second-Phase Particles in Zirconium Binary Alloys
- P. Barberis, E. Ahlberg, +7 authors B. Lehtinen
- Materials Science
- 2002