Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Claddings, ANS Portland, pp.405-412, 1997. ,
Optimization of PWR Behaviour of Stress-relieved Zircaloy-4 ,
, Cladding Tubes by Upgrading the Manufacturing and Inspection Process, Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, pp.329-348, 1994.
Framatome and FCF Recent Operating Experience and Advanced Features to Increase Performance Reliability, ANS Portland, pp.31-38, 1997. ,
Ultra Low Tin Quaternary Alloys PWR Performance-Impact of Tin Content on Corrosion Resistance, Irradiation Growth and Mechanical Properties, Zirconium in the Nuclear Industry: Sixteenth International Symposium, ASTM STP 1529, pp.801-826, 2012. ,
Ultra low tin Zr1NbSnFe quaternary alloys-perspectives for structural components in PWR Fuel assemblies, Proceedings of Topfuel, pp.417-421, 2012. ,
Q12 ultra low tin quaternary alloy for structural components in PWR fuel assemblies, Proceeding of Topfuel, pp.151-159, 2015. ,
Effect of irradiation on the Microstructure of Zircaloy-4, Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, pp.521-548, 1994. ,
Irradiation Creep and Growth Behaviour, and Microstructural Evolution of Advanced Zr-Base Alloys, Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, pp.51-73, 2000. ,
Microstructural Stability of M5? Alloy Irradiated up to High Neutron Fluences, Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467, pp.175-201, 2006. ,
The Evolution of Microstructure and Deformation stability in Zr-Nb-(Sn, Fe) Alloys under Neutron Irradiation, Zirconium in the Nuclear Industry: Sixteenth International Symposium, ASTM STP 1529, pp.37-66, 2012. ,
Microstructural Evolution of M5 Alloy Irradiated in PWRs up to High Fluences. Comparison with Other Zr-Based Alloys, Zirconium in the Nuclear Industry: 17 th International Symposium, vol.1543, pp.759-799, 2015. ,
Influence of Neutron Irradiation and Dislocation Structure and Phase Composition of Zr-Base Alloys, Eleventh International Symposium, ASTM STP 1295, pp.603-622, 1996. ,
Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys, Zirconium in the Nuclear Industry : 15th International Symposium, ASTM STP 1505, pp.724-743, 2009. ,
Influence of Structure-Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth, Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467, pp.666-685, 2006. ,
In PWR Comprehension Study of High Burn-up corrosion and Growth Behavior of M5 ® and recrystallised Low-Tin Zircaloy 4, Zirconium in the Nuclear Industry: Fifteenth International Symposium, ASTM STP 1505, pp.430-456, 2009. ,
A review of microstructure evolution in zirconium alloys during irradiation, Journal of Nuclear Materials, vol.159, pp.190-218, 1988. ,
Influence of iron in the nucleation of the <c> component dislocation loops in irradiated zircaloy-4, Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, pp.633-638, 1996. ,
Amorphisation Kinetics of Zr(Cr,Fe)2 under ions irradiation, Beam Solid Interactions: Fondamentals and applications, Book Series : Material Research Society Symposium Proceedings, vol.279, pp.517-522, 1993. ,
Effect of irradiation on the precipitate stability in Zr alloys, Journal of Nuclear Materials, vol.205, pp.445-451, 1993. ,
Precipitation in Zr-2.5 wt% Nb during Neutron Irradiation, Phase Stability During Irradiation Symposium, pp.587-599, 1981. ,
Microstructural and Microchemical Studies of Zr-2.5Nb Pressure Tube Alloy, Journal of Nuclear Materials, vol.205, pp.251-257, 1993. ,
Influence of Neutron Irradiation and Dislocation Structure and Phase Composition of Zr-Base Alloys, Zirconium in the Nuclear Industry: Seven International Symposium, ASTM STP 939, pp.603-622, 1987. ,
Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth, Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423, pp.759-779, 2002. ,
Stability of Precipitates in the anisotropic ?-Zr Matrix under Irradiation, Journal of Nuclear Materials, vol.185, pp.214-223, 1991. ,
Construction of Radiation-modified Phase Diagrams under Cascade-producing Irradiation, Journal of Nuclear Materials, vol.305, pp.134-152, 2002. ,
Mechanisms and kinetics of precipitate restructuring during irradiation, Journal of Nuclear Materials, vol.273, pp.208-213, 1999. ,
Diffusion and Precipitation under Irradiation, Diffusion in Materials, pp.339-336, 1990. ,
Threedimensional finite element analysis of stresses and energy density distribution around ?' before coarsening loaded in the [110]-direction in Ni-based superalloy, Material Science and Engineering A, vol.352, pp.300-307, 2003. ,
Evolution of Dislocation and Precipitate Structure in Zr Alloys Under Long-Term Irradiation, Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, pp.105-121, 2000. ,
Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System, Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423, pp.361-383, 2002. ,
, Study of Nb and Fe Precipitates in a-Phase Temperature Range (400 to 550C) in Zr-Nb
, Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467, pp.81-101, 2006.
Iron redistribution in a zirconium alloy after neutron and proton irradiation studied by energy-dispersive X-ray spectroscopy (EDX) using an aberration-corrected (scanning) transmission electron microscope, Journal of Nuclear Materials, vol.454, pp.387-397, 2014. ,
Evolution microstructurale des alliages de zirconium sous irradiation -Liens avec le phénomène de croissance ,
Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation Growth Behavior of Zirconium Alloy Variants, 18th International Symposium ,
Effect of alloying elements on the formation of <c>-component loops in Zr alloy Excel under heavy ion irradiation, Journal of Material Research, vol.30, issue.9, pp.1310-1334, 2015. ,