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G. Repetto

LWR severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT0
2003 · B Clément, N Hanniet-Girault, et al. · Nuclear Engineering and Design · 129
Experimental program on debris reflooding (PEARL) – Results on PRELUDE facility
2013 · Georges Repetto, Thierry Garcin, et al. · Nuclear Engineering and Design · 40
Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests
2012 · O. de Luze, T. Haste, et al. · Annals of Nuclear Energy · 37
Late phase fuel degradation in the Phébus FP tests
2013 · M. Barrachin, O. de Luze, et al. · Annals of Nuclear Energy · 32
Investigations on boron carbide oxidation for nuclear reactors safety—General modelling for ICARE/CATHARE code applications
2007 · N. Seiler, F. Bertrand, et al. · Nuclear Engineering and Design · 29
Experimental investigation on reflooding of debris beds
2014 · S. Leininger, R. Kulenovic, et al. · Annals of Nuclear Energy · 24
B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments
2009 · G. Repetto, O. De Luze, et al. · Progress in Nuclear Energy · 24
Velocity field and flow redistribution in a ballooned 7×7 fuel bundle measured by magnetic resonance velocimetry
2020 · A.V.S. Oliveira, D. Stemmelen, et al. · Nuclear Engineering and Design · 17
The R&D PERFROI project on Thermal mechanical and thermal hydraulics behaviors of a fuel rod assembly during a Loss Of Coolant Accident
2015 · Repetto, Georges, Dominguez, Cristina, et al. · HAL · 17
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Quench Front Progression in a Superheated Porous Medium: Experimental Analysis and Model Development
2024 · Bachrata, Andrea, Fichot, Florian, et al. · Open Archive Toulouse Archive Ouverte (University of Toulouse) · 13
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Parametric effects on the flow redistribution in ballooned bundles evaluated by magnetic resonance velocimetry
2021 · A.V.S. Oliveira, D. Stemmelen, et al. · Experimental Thermal and Fluid Science · 12
Quenching of a highly superheated porous medium by injection of water
2012 · F Fichot, A Bachrata, et al. · Journal of Physics Conference Series · 6
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Code Simulation of Quenching of a High Temperature Debris Bed: Model Improvement and Validation With Experimental Results
2012 · A. Bachrata, F. Fichot, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 6
Analyses of the Phébus FPT3 Experiment Using the Severe Accident Codes ATHLET-CD, ICARE/CATHARE, and MELCOR
2011 · Georges Repetto, Olivier de Luze, et al. · Nuclear Technology · 5
COAL reflooding experiments during a loss of coolant Accident: Effect of the water flow rate, the pressure and the rod power with ballooned rods
2024 · G. Repetto, Q. Grando, et al. · Nuclear Engineering and Design · 4
Coal Experiments Investigating the Reflooding of a 7 X 7 Rods Bundle During a Loss of Coolant Accident -- Effect of a Partially Blocked Area with Ballooned Rods
2023 · G. Repetto, Q. Grando, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 3
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Non-local equilibrium two-phase flow model with phase change in porous media and its application to reflooding of a severely damaged reactor core
2012 · A. Bachrata, F. Fichot, et al. · AIP conference proceedings · 3
Estimation du transfert de chaleur gouttes/paroi en situation d'APRP pour un REP.
2009 · Michel GrAdeck, Denis Maillet, et al. · La Houille Blanche · 3
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European research on the corium issues within the SARNET network of excellence
2008 · Christophe Journeau, T. Wiss, et al. · 3
Final Interpretation Report of the PHEBUS test FPT0: Bundle Aspects
2007 · Kirill Müller, B. Tóth, et al. · 3
COAL Experiments Investigating the Reflooding of a 7 × 7 Rod Bundle During a Loss-of-Coolant Accident: Effect of a Partially Blocked Area with Ballooned Rods
2024 · Georges Repetto, Quentin Grando, et al. · Nuclear Science and Engineering · 2
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Contribution to modeling of the reflooding of a severely damaged reactor core using PRELUDE experimental results
2012 · Andrea Bachrata, F. Fichot, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
VIKTORIA experiments in the frame of R&D project on sump filtration during a loss of coolant accident
2024 · Georges Repetto, Jean-François Trigeol, et al. · Nuclear Engineering and Design · 1
Experimental Study of the Effect of Neighboring Rods in Fuel Cladding Deformation Under LOCA Conditions
2022 · Cristina Dominguez, Pauline Lacote, et al. · TopFuel Light Water Reactor Fuel Performance Conference (TopFuel) · 1
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Icone19-43044 Reflooding of a Severely Damaged Reactor Core : Experimental Analysis and Modelling
2011 · A. Bachrata, F. Fichot, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
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Works count: 68
Citation count: 448
H-index: 11
I10-index: 11
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