| Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors JC Brachet, I Idarraga-Trujillo, M Le Flem, M Le Saux, V Vandenberghe, ... Journal of Nuclear Materials 517, 268-285, 2019 | 268 | 2019 |
| High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process JC Brachet, E Rouesne, J Ribis, T Guilbert, S Urvoy, G Nony, ... Corrosion Science 167, 108537, 2020 | 234 | 2020 |
| 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 | 125 | 2015 |
| Assessment at CEA of coated nuclear fuel cladding for LWRs with increased margins in LOCA and beyond LOCA conditions I Idarraga-Trujillo, M Le Flem, JC Brachet, M Le Saux, D Hamon, S Muller, ... LWR Fuel Performance Meeting, Top Fuel 2013 2, 860-867, 2013 | 106 | 2013 |
| Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25°C and 480°C under various stress states, including RIA loading conditions M Le Saux, J Besson, S Carassou, C Poussard, X Averty Engineering Failure Analysis 17 (3), 683-700, 2010 | 83 | 2010 |
| A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions M Le Saux, J Besson, S Carassou, C Poussard, X Averty Journal of Nuclear Materials 378 (1), 60-69, 2008 | 64 | 2008 |
| Behavior of chromium coated M5TM claddings under LOCA conditions JC Brachet, M Dumerval, V Lezaud-Chailioux, M Le Saux, E Rouesne, ... WRFPM 2017 Water Reactor Fuel Performance Meeting, 2017 | 59 | 2017 |
| Behavior under LOCA conditions of enhanced accident tolerant chromium coated zircaloy-4 claddings JC Brachet, M Le Saux, V Lezaud-Chaillioux, M Dumerval, Q Houmaire, ... Topfuel 2016-Light Water Reactor (LWR) Fuel Performance Meeting, 2016 | 58 | 2016 |
| High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubes A Michau, F Maury, F Schuster, F Lomello, JC Brachet, E Rouesne, ... Surface and Coatings Technology 349, 1048-1057, 2018 | 49 | 2018 |
| 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, ... Fontevraud 8 - Contribution of Materials Investigations and Operating …, 2014 | 49 | 2014 |
| Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 C in relation with oxygen diffusion/partitioning and post-quench ductility JC Brachet, M Le Saux, J Bischoff, H Palancher, R Chosson, E Pouillier, ... Journal of Nuclear Materials 533, 152106, 2020 | 44 | 2020 |
| “Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe … JC Brachet, D Hamon, M Le Saux, V Vandenberghe, C Toffolon-Masclet, ... Journal of Nuclear Materials 488, 267-286, 2017 | 34 | 2017 |
| Influence of Pre-Transient Oxide on LOCA High Temperature Steam Oxidation and Post-Quench mechanical Properties of Zircaloy-4 and M5™ cladding M Le Saux, JC Brachet, V Vandenberghe, D Gilbon, JP Mardon, ... 2011 Water Reactor Fuel Performance Meeting, 11-14, 2011 | 34 | 2011 |
| Experimental investigation and theoretical modelling of induced anisotropy during stress-softening of rubber G Marckmann, G Chagnon, M Le Saux, P Charrier International Journal of Solids and Structures 97, 554-565, 2016 | 33 | 2016 |
| In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature D Gosset, M Le Saux Journal of Nuclear Materials 458, 245-252, 2015 | 32 | 2015 |
| 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 | 31 | 2020 |
| Behavior of cr-coated m5 claddings during and after high temperature steam oxidationfrom 800c up to 1500c JC Brachet, T Guilbert, M Lesaux, J Rousselot, G Nony, ... Topfuel 2018, 2018 | 31 | 2018 |
| Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 and M5Framatome alloys M Le Saux, JC Brachet, V Vandenberghe, E Rouesne, S Urvoy, A Ambard, ... Journal of Nuclear Materials 518, 386-399, 2019 | 28 | 2019 |
| DLI-MOCVD CrxCy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions JC Brachet, S Urvoy, E Rouesne, G Nony, M Dumerval, M Le Saux, F Ott, ... Journal of Nuclear Materials 550, 152953, 2021 | 27 | 2021 |
| Fatigue criteria for short fiber-reinforced thermoplastic validated over various fiber orientations, load ratios and environmental conditions P Santharam, Y Marco, V Le Saux, M Le Saux, G Robert, I Raoult, ... International Journal of Fatigue 135, 105574, 2020 | 27 | 2020 |
