Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems C Guéneau, N Dupin, B Sundman, C Martial, JC Dumas, S Gossé, ... Journal of nuclear materials 419 (1-3), 145-167, 2011 | 263 | 2011 |
Thermodynamic assessment of the uranium–oxygen system C Guéneau, M Baichi, D Labroche, C Chatillon, B Sundman Journal of Nuclear Materials 304 (2-3), 161-175, 2002 | 251 | 2002 |
Recent advances in the study of the UO2–PuO2 phase diagram at high temperatures R Böhler, MJ Welland, D Prieur, P Cakir, T Vitova, T Pruessmann, ... Journal of Nuclear Materials 448 (1-3), 330-339, 2014 | 106 | 2014 |
Thermodynamic modelling of the plutonium–oxygen system C Guéneau, C Chatillon, B Sundman Journal of Nuclear Materials 378 (3), 257-272, 2008 | 101 | 2008 |
Modeling and simulation of nuclear fuel materials R Devanathan, L Van Brutzel, A Chartier, C Guéneau, AE Mattsson, ... Energy & Environmental Science 3 (10), 1406-1426, 2010 | 100 | 2010 |
Experimental and thermodynamic assessment of the Fe Zr system C Servant, C Gueneau, I Ansara Journal of Alloys and Compounds 220 (1-2), 19-26, 1995 | 96 | 1995 |
Thermodynamic study of the U–Si system A Berche, C Rado, O Rapaud, C Guéneau, J Rogez Journal of Nuclear Materials 389 (1), 101-107, 2009 | 87 | 2009 |
Calphad thermodynamic description of some binary systems involving U A Berche, N Dupin, C Guéneau, C Rado, B Sundman, JC Dumas Journal of nuclear materials 411 (1-3), 131-143, 2011 | 80 | 2011 |
Thermodynamic and thermophysical properties of the actinide oxides C Guéneau, A Chartier, P Fossati, L Van Brutzel, P Martin Elsevier, 2020 | 69 | 2020 |
TAF-ID: An international thermodynamic database for nuclear fuels applications C Gueneau, N Dupin, L Kjellqvist, E Geiger, M Kurata, S Gosse, ... Calphad 72, 102212, 2021 | 65 | 2021 |
Liquid immiscibility in a (O, U, Zr) model corium C Guéneau, V Dauvois, P Pérodeaud, C Gonella, O Dugne Journal of nuclear materials 254 (2-3), 158-174, 1998 | 62 | 1998 |
Laser melting of uranium carbides CA Utton, F De Bruycker, K Boboridis, R Jardin, H Noel, C Guéneau, ... Journal of Nuclear Materials 385 (2), 443-448, 2009 | 58 | 2009 |
FeAl3Si2 C Gueneau, C Servant, F d'Yvoire, N Rodier Acta Crystallographica Section C: Crystal Structure Communications 51 (2 …, 1995 | 54 | 1995 |
A thermodynamic study of the Pu–Am–O system P Gotcu-Freis, JY Colle, C Guéneau, N Dupin, B Sundman, RJM Konings Journal of Nuclear Materials 414 (3), 408-421, 2011 | 50 | 2011 |
On the melting behaviour of uranium/plutonium mixed dioxides with high-Pu content: A laser heating study F De Bruycker, K Boboridis, RJM Konings, M Rini, R Eloirdi, C Guéneau, ... Journal of Nuclear Materials 419 (1-3), 186-193, 2011 | 48 | 2011 |
A thermodynamic approach for advanced fuels of gas-cooled reactors C Guéneau, S Chatain, S Gossé, C Rado, O Rapaud, J Lechelle, ... Journal of nuclear materials 344 (1-3), 191-197, 2005 | 48 | 2005 |
Chemical compatibility between UO2 fuel and SiC cladding for LWRs. Application to ATF (Accident-Tolerant Fuels) J Braun, C Guéneau, T Alpettaz, C Sauder, E Brackx, R Domenger, ... Journal of Nuclear Materials 487, 380-395, 2017 | 41 | 2017 |
Extreme multi-valence states in mixed actinide oxides E Epifano, M Naji, D Manara, AC Scheinost, C Hennig, J Lechelle, ... Communications Chemistry 2 (1), 59, 2019 | 39 | 2019 |
Contribution to the thermodynamic description of the corium–The U-Zr-O system A Quaini, C Guéneau, S Gossé, N Dupin, B Sundman, E Brackx, ... Journal of Nuclear Materials 501, 104-131, 2018 | 38 | 2018 |
Diffusion model of the non-stoichiometric uranium dioxide E Moore, C Guéneau, JP Crocombette Journal of Solid State Chemistry 203, 145-153, 2013 | 38 | 2013 |