| The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr–Sn–Nb alloys J Wei, P Frankel, E Polatidis, M Blat, A Ambard, RJ Comstock, ... Acta Materialia 61 (11), 4200-4214, 2013 | 184 | 2013 |
| Residual stresses and tetragonal phase fraction characterisation of corrosion tested Zircaloy-4 using energy dispersive synchrotron X-ray diffraction E Polatidis, P Frankel, J Wei, M Klaus, RJ Comstock, A Ambard, S Lyon, ... Journal of Nuclear Materials 432 (1-3), 102-112, 2013 | 146 | 2013 |
| The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys A Couet, AT Motta, A Ambard Corrosion Science 100, 73-84, 2015 | 136 | 2015 |
| On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRs fuel F Schuster, F Lomello, A Billard, G Velisa, E Monsifrot, J Bischoff, ... TopFuel 2015-Reactor Fuel Performance Meeting, 2015 | 134 | 2015 |
| Identification and characterization of a new zirconium hydride Z Zhao, JP Morniroli, A Legris, A Ambard, Y Khin, L Legras, M Blat‐Yrieix Journal of microscopy 232 (3), 410-421, 2008 | 131 | 2008 |
| Role of interphases in the deformation mechanisms of an α/β titanium alloy at 20 K A Ambard, L Guétaz, F Louchet, D Guichard Materials Science and Engineering: A 319, 404-408, 2001 | 94 | 2001 |
| Studies regarding corrosion mechanisms in zirconium alloys M Preuss, P Frankel, S Lozano-Perez, D Hudson, E Polatidis, N Ni, J Wei, ... Journal of ASTM International 8 (9), 1-23, 2011 | 87 | 2011 |
| Characterization of zirconium hydrides and phase field approach to a mesoscopic-scale modeling of their precipitation Z Zhao, M Blat-Yrieix, JP Morniroli, A Legris, L Thuinet, Y Kihn, A Ambard, ... ASTM International 5 (3), 2008 | 75 | 2008 |
| The cyclic nature of corrosion of Zr and Zr-Sn in high-temperature water (633 K): a long-term in situ impedance spectroscopic study J Schefold, D Lincot, A Ambard, O Kerrec Journal of The Electrochemical Society 150 (10), B451, 2003 | 66 | 2003 |
| In-situ electrochemical impedance spectroscopy measurements of zirconium alloy oxide conductivity: Relationship to hydrogen pickup A Couet, AT Motta, A Ambard, D Livigni Corrosion Science 119, 1-13, 2017 | 55 | 2017 |
| CEA studies on advanced nuclear fuel claddings for enhanced Accident Tolerant LWRs Fuel (LOCA and beyond LOCA conditions) JC Brachet, C Lorrette, A Michaux, C Sauder, I Idarraga-Trujillo, ... Proceedings of the Fontevraud 8, 2014 | 54 | 2014 |
| Dislocation dynamics simulations of interactions between gliding dislocations and radiation induced prismatic loops in zirconium J Drouet, L Dupuy, F Onimus, F Mompiou, S Perusin, A Ambard Journal of Nuclear Materials 449 (1-3), 252-262, 2014 | 48 | 2014 |
| Mesoscale modeling of coherent zirconium hydride precipitation under an applied stress L Thuinet, A Legris, L Zhang, A Ambard Journal of nuclear materials 438 (1-3), 32-40, 2013 | 46 | 2013 |
| A new model to predict the oxidation kinetics of zirconium alloys in a pressurized water reactor V Bouineau, A Ambard, G Bénier, D Pêcheur, J Godlewski, L Fayette, ... ASTM International, 2008 | 39 | 2008 |
| A new scenario for‹ c› vacancy loop formation in zirconium based on atomic-scale modeling B Christiaen, C Domain, L Thuinet, A Ambard, A Legris Acta Materialia 179, 93-106, 2019 | 37 | 2019 |
| Quantitative phase field model for dislocation sink strength calculations H Rouchette, L Thuinet, A Legris, A Ambard, C Domain Computational materials science 88, 50-60, 2014 | 35 | 2014 |
| Autoclave study of zirconium alloys with and without hydride rim J Wei, P Frankel, M Blat, A Ambard, RJ Comstock, L Hallstadius, S Lyon, ... Corrosion engineering, science and technology 47 (7), 516-528, 2012 | 35 | 2012 |
| Toward a better understanding of dimensional changes in Zircaloy-4: what is the impact induced by hydrides and oxide layer? M Blat-Yrieix, A Ambard, F Foct, A Miquet, S Beguin, N Cayet ASTM International, 2008 | 35 | 2008 |
| Understanding Crack Formation at the Metal/Oxide Interface During Corrosion of Zircaloy-4 Using a Simple Mechanical Model 16th International Symposium on Zirconium in the … A Ly, A Ambard, M Blat-Yrieix, L Legras, P Frankel, M Preuss, C Curfs, ... Zirconium in the Nuclear Industry: 16th International Symposium, 2012 | 34* | 2012 |
| Breakaway oxidation of zirconium alloys exposed to steam around 1000 C M Le Saux, JC Brachet, V Vandenberghe, A Ambard, R Chosson Corrosion Science 176, 108936, 2020 | 33 | 2020 |
Alexandre LegrisPr, Université Lille 1Verified email at univ-lille1.fr
