| Synchrotron diffraction study of dissolution and precipitation kinetics of hydrides in Zircaloy-4 O Zanellato, M Preuss, JY Buffiere, F Ribeiro, A Steuwer, J Desquines, ... Journal of Nuclear Materials 420 (1-3), 537-547, 2012 | 139 | 2012 |
| The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA) J Desquines, DA Koss, AT Motta, B Cazalis, M Petit Journal of Nuclear Materials 412 (2), 250-267, 2011 | 136 | 2011 |
| Summary and interpretation of the CABRI REP-Na program J Papin, B Cazalis, JM Frizonnet, J Desquines, F Lemoine, ... Nuclear technology 157 (3), 230-250, 2007 | 121 | 2007 |
| The PROMETRA program: Fuel cladding mechanical behavior under high strain rate B Cazalis, J Desquines, C Poussard, M Petit, Y Monerie, C Bernaudat, ... Nuclear technology 157 (3), 215-229, 2007 | 80 | 2007 |
| Influence of temperature and hydrogen content on stress-induced radial hydride precipitation in Zircaloy-4 cladding J Desquines, D Drouan, M Billone, MP Puls, P March, S Fourgeaud, ... Journal of Nuclear Materials 453 (1-3), 131-150, 2014 | 61 | 2014 |
| Mechanical response of oxidized Zircaloy-4 cladding material submitted to a ring compression test V Busser, MC Baietto-Dubourg, J Desquines, C Duriez, JP Mardon Journal of Nuclear Materials 384 (2), 87-95, 2009 | 50 | 2009 |
| Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior J Desquines, B Cazalis, C Bernaudat, C Poussard, X Averty, P Yvon ASTM Special Technical Publication 1467, 851, 2006 | 38 | 2006 |
| Embrittlement of pre-hydrided Zircaloy-4 by steam oxidation under simulated LOCA transients J Desquines, D Drouan, S Guilbert, P Lacote Journal of Nuclear Materials 469, 20-31, 2016 | 33 | 2016 |
| Characterization of Oxygen Distribution in LOCA Situations C Duriez, S Guilbert, A Stern, C Grandjean, B Ladislav, J Desquines Journal of ASTM International 8 (2), 2010 | 26 | 2010 |
| Identification of the steady-state creep behavior of Zircaloy-4 claddings under simulated Loss-Of-Coolant Accident conditions based on a coupled experimental/numerical approach D Campello, N Tardif, M Moula, MC Baietto, M Coret, J Desquines International Journal of Solids and Structures 115, 190-199, 2017 | 25 | 2017 |
| Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation and post-quench mechanical properties S Guilbert, P Lacote, G Montigny, C Duriez, J Desquines, C Grandjean ASTM STP 1523, 2013 | 25 | 2013 |
| Modelling of corrosion induced stresses during Zircaloy-4 oxidation in air V Busser, J Desquines, S Fouquet, MC Baietto, JP Mardon Materials Science Forum 595, 419-427, 2008 | 25 | 2008 |
| Fracture mechanics approach for failure mode analysis in CABRI and NSRR RIA tests V Georgenthum, T Sugiyama, Y Udagawa, T Fuketa, J Desquines interpretation 7, 8, 2008 | 17 | 2008 |
| The PROMETRA program: a reliable material database for highly irradiated Zircaloy-4, ZirloTM and M5TM fuel claddings B Cazalis, C Bernaudat, P Yvon, J Desquines, C Poussard, X Averty 18th international conference on structural mechanics in reactor technology …, 2005 | 16 | 2005 |
| Influence of hydrogen on the oxygen solubility in Zircaloy-4 S Guilbert-Banti, P Lacote, G Taraud, P Berger, J Desquines, C Duriez Journal of Nuclear Materials 469, 228-236, 2016 | 15 | 2016 |
| Experimental study and modelling of the phase transformation of Zircaloy-4 alloy under high thermal transients T Jailin, N Tardif, J Desquines, M Coret, MC Baietto, V Georgenthum Materials Characterization 162, 110199, 2020 | 14 | 2020 |
| The plane strain tests in the PROMETRA program B Cazalis, J Desquines, S Carassou, T Le Jolu, C Bernaudat Journal of Nuclear Materials 472, 127-142, 2016 | 14 | 2016 |
| Influence of outer zirconia transient cracking and spalling on thermomechanical behaviour of high burnup fuel rod submitted to RIA V Georgenthum, J Desquines, V Bessiron Journal of Nuclear Science and Technology 43 (9), 1089-1096, 2006 | 14 | 2006 |
| Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation S Guilbert-Banti, A Viretto, J Desquines, C Duriez Journal of Nuclear Materials 548, 152854, 2021 | 13 | 2021 |
| Thermo-mechanical behavior of Zircaloy-4 claddings under simulated post-DNB conditions T Jailin, N Tardif, J Desquines, P Chaudet, M Coret, MC Baietto, ... Journal of Nuclear Materials 531, 151984, 2020 | 12 | 2020 |
Baietto Marie-ChristineDirectrice de Recherches, INSA Lyon, UMR 5259LaMCoSВерификована је имејл адреса на insa-lyon.fr