Georges REPETTO Chef de projet

Publications

Article dans une revue (12)

VIKTORIA experiments in the frame of R&D project on sump filtration during a Loss Of Coolant Accident: effect of the type of filter, the mass of fiber and the presence of zinc Georges Repetto,Jean-François Trigeol,Vojtech Soltesz Nuclear Engineering and Technology, In press, pp.104239. ⟨10.1016/j.net.2026.104239⟩ Article dans une revue hal-05496734v2
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 Georges Repetto,Quentin Grando,Stephane Eymery,Richard van Lochem Nuclear Science and Engineering, 2025, Selected papers from the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), 199 (10), pp.1563-1580. ⟨10.1080/00295639.2024.2437934⟩ Article dans une revue irsn-04879532v1
Effect of neighbouring rods in cladding deformation and rupture opening size during loss of coolant accidents Cristina Dominguez,Tatiana Taurines,Georges Repetto Journal of Nuclear Materials, 2025, 612, pp.155848. ⟨10.1016/j.jnucmat.2025.155848⟩ Article dans une revue hal-05086681v1
VIKTORIA experiments in the frame of R&D project on sump filtration during a Loss Of Coolant Accident Georges Repetto,Jean-François Trigeol,Vojtech Soltész Nuclear Engineering and Design, 2024, 428 (113563), pp.1-11. ⟨10.1016/j.nucengdes.2024.113563⟩ Article dans une revue irsn-04738309v1
COAL reflooding experiments during a loss of coolant Accident: Effect of the water flow rate, the pressure and the rod power with ballooned rods Georges Repetto,Quentin Grando,Stephane Eymery,R. van Lochem Nuclear Engineering and Design, 2024, 429, pp.113641. ⟨10.1016/j.nucengdes.2024.113641⟩ Article dans une revue irsn-04751843v1
Parametric effects on the flow redistribution in ballooned bundles evaluated by magnetic resonance velocimetry A.V.S. Oliveira,Didier Stemmelen,S. Leclerc,T. Glantz,Alexandre Labergueet al. Experimental Thermal and Fluid Science, 2021, 125, pp.110383. ⟨10.1016/j.expthermflusci.2021.110383⟩ Article dans une revue hal-03162585v1
Velocity field and flow redistribution in a ballooned 7x7 fuel bundle measured by magnetic resonance velocimetry Arthur Oliveira,Didier Stemmelen,Sebastien Leclerc,Tony Glantz,Alexandre Labergueet al. Nuclear Engineering and Design, 2020, 369, pp.110828. ⟨10.1016/j.nucengdes.2020.110828⟩ Article dans une revue hal-02940079v1
Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests O. de Luze,T. Haste,M. Barrachin,G. Repetto Annals of Nuclear Energy, 2013, 61, pp.23-35. ⟨10.1016/j.anucene.2012.10.026⟩ Article dans une revue istex hal-03113377v1
Quench front progression in a superheated porous medium: experimental analysis and model development Andrea Bachrata,Florian Fichot,Georges Repetto,Michel Quintard,Joëlle Fleurot Journal of Energy and Power Engineering, 2013, 7, pp.514-523 Article dans une revue hal-04312479v1
Late phase fuel degradation in the Phébus FP tests M. Barrachin,O. de Luze,T. Haste,G. Repetto Annals of Nuclear Energy, 2013, 61, pp.36-53. ⟨10.1016/j.anucene.2013.03.041⟩ Article dans une revue istex hal-03111570v1
Analyses of the phébus FPT3 experiment using the severe accident codes ATHLET-CD, ICARE/CATHARE, and MELCOR G. Repetto,O. De Luze,T. Drath,M. K. Koch,T. Hollandset al. Nuclear Technology, 2011, 176 (3), pp.352--371. ⟨10.13182/NT11-A13313⟩ Article dans une revue hal-02962929v1
B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments G. Repetto,O. de Luze,N. Seiler,K. Trambauer,H. Austregesiloet al. Progress in Nuclear Energy, 2010, 52 (1), pp.37-45. ⟨10.1016/j.pnucene.2009.09.017⟩ Article dans une revue istex hal-02972637v1

Communication dans un congrès (30)

VIKTORIA experiments in the frame of R&D project on sump filtration during a Loss Of Coolant Accident: effect of the type of filter, the mass of fiber and the presence of zinc Georges Repetto,Jean-François Trigeol,Vojtech Soltesz 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21), Thermal-Hydraulics Division of the Korean Nuclear Society (KNS); American Nuclear Society, Aug 2025, Busan, South Korea Communication dans un congrès hal-05497002v1
On the progress made in safety assessment and severe accident management as part of the french Fukushima post-accident research programme Ahmed Bentaib,Renaud Meignen,Laurent Cantrel,Sandrine Morin,Georges Repetto The 11th European Review Meeting on Severe Accident Research (ERMSAR2024), Königlich Technische Hochschule Stockholm (KTH), May 2024, Stockholm, Sweden Communication dans un congrès irsn-04858131v1
COAL reflooding experiments during a Loss Of coolant Accident: Effect of the water flow rate and the residual power with ballooned rods Georges Repetto,Quentin Grando,Stephane Eymery,R. Fortman,R. van Lochem 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14), Canadian Nuclear Society (CNS), Aug 2024, Vancouver, Canada Communication dans un congrès hal-05539464v1
COAL experiments investigating the reflooding of a 7 X 7 rod bundle during a Loss Of coolant Accident: Effect of a partially blocked area with ballooned rods Georges Repetto,Quentin Grando,B. Bruyère,Stephane Eymery,R. Fortmanet al. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), American Nuclear Society, Aug 2023, Washington, United States. pp.1910-1923, ⟨10.13182/NURETH20-40021⟩ Communication dans un congrès irsn-04200520v1
Coal experiments investigating the reflooding of a 7 x 7 rods bundle during a loss of coolant accident thermalhydraulics results Georges Repetto,Quentin Grando,Stephane Eymery,B. Bruyère The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ANS - American Nuclear Society, Mar 2022, Bruxelles (ON LINE), Belgium Communication dans un congrès irsn-04100311v1
Simulation de l'écoulement dispersé vapeur/gouttes dans des conditions d'APRP Juan Esteban Luna Valencia,Arthur V S Oliveira,Alexandre Labergue,Tony Glantz,Georges Repettoet al. 29e Congrès français de thermique, Société Française de Thermique, Jun 2021, Belfort, France. ⟨10.25855/SFT2021-037⟩ Communication dans un congrès hal-03529904v1
Operation Extension of 900MWe NPPs: French TSO Main Conclusions regarding Long Term Sump Performance after a Loss of Coolant Accident Jean-François Trigeol,Pariaud Emilie,Dixneuf Estelle,Georges Repetto RCCS - 2021 - Specialist Workshop on Reactor core and containment cooling systems – long term management and reliability, OECD/NEA, Oct 2021, Virtual (on line), Slovakia. 5 p Communication dans un congrès irsn-04113763v1
VIKTORIA experiments on sump filtration during a Loss Of Coolant Accident (DBA) Georges Repetto,Benoit Migot,Vojtech Soltesz Specialist Workshop on Reactor core and containment cooling systems – long term management and reliability, OECD NEA, Oct 2021, Virtual Worshop, Slovakia Communication dans un congrès irsn-04113818v1
VIKTORIA experiments investigating the filtering system in the sump of a pwr after a Loss Of Coolant Accident : Part II Downstream effects Georges Repetto,Benoît Migot,Caroline Heib,Vojtech Soltesz 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, American Nuclear Society, Aug 2019, Portland, United States. pp.ISBN 9781510893450 Communication dans un congrès irsn-04113583v1
Viktoria experiments investigating the filtering system in the sump of a pwr after a loss of coolant accident : Part I Physical /chemical effects on strainer head loss evolution Georges Repetto,Benoit Migot,Jean-François Trigeol,Vojtech Soltesz NURETH 2019 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, PORTLAND, United States. pp.407-420 Communication dans un congrès irsn-04111911v1
Analyse des transferts thermiques d'un écoulement vertical vapeur/gouttes dans une géométrie tubulaire Juan David Peña Carrillo,Arthur V S Oliveira,Alexandre Labergue,Tony Glantz,Georges Repettoet al. 27e Congrès français de thermique, Jun 2019, Nantes, France Communication dans un congrès hal-03529839v1
Identification des transferts thermiques d'un écoulement vertical vapeur/gouttes dans une géométrie tubulaire Juan David Peña Carrillo,Alexandre Labergue,Tony Glantz,Georges Repetto,Michel Gradeck Congrès français de thermique, May 2018, Pau, France Communication dans un congrès hal-03529820v1
CoreSOAR Core Degradation SOAR Update Status May 2017 T. Haste,M. Barrachin,F. Fichot,G. Repetto,A. Miassoedovet al. 8th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland Communication dans un congrès hal-02418127v1
CORE COOLABILITY IN LOSS OF COOLANT ACCIDENT: THE COAL EXPERIMENTS INVESTIGATING THE THERMAL HYDRAULICS OF A ROD BUNDLE WITH BLOCKED AREA DURING THE REFLOODING Georges Repetto,Tony Glantz,Gaétan Guillard,Benoit Bruyère,Quentin Grando 2017 International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), American Nuclear Society, Sep 2017, Xi’an, China Communication dans un congrès irsn-04474794v1
The PERFROI project investigating the thermal mechanical behaviour of a fuel rod assembly during a loss of coolant accident Georges Repetto,Cristina Dominguez,Tatiana Taurines Water Reactor Fuel Performance Meeting 2017 (TopFuel 2017), Korean Nuclear Society (KNS), Sep 2017, Jeju City, Jeju Island, South Korea Communication dans un congrès hal-05539419v1
Heat transfer inside a blocked region of a rod bundle during a LOCA-simulations and experiments Juan David Peña Carrillo,Michel Gradeck,Alexandre Labergue,Tony Glantz,Georges Repetto 9th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics (EXHFT-9), Jun 2017, Iguazu, Brazil Communication dans un congrès hal-03530191v1
Study on Heat Transfer Inside a Blocked Region of a Rod Bundle During a LOCA - Model and Experimental Approach Juan-David Peña-Carrillo,Tony Glantz,Georges Repetto,Alexandre Labergue,Michel Gradeck 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-17, Sep 2017, Xian, China Communication dans un congrès hal-03530147v1
Thermal hydraulics behavior of a rod bundle with partially blocked area during the reflooding phase of the Loss Of Cooling Accident Georges Repetto,Benoit Bruyère,Stephane Eymery,Tony Glantz NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, American Nuclear Society and Korean Nuclear Society, Oct 2016, Gyeongju, South Korea Communication dans un congrès irsn-04474648v1
Experimental study on heat transfer inside a blocked region of a rod bundle during a LOCA Juan David Peña Carrillo,Tony Glantz,Georges Repetto,Alexandre Labergue,Michel Gradeck 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operations and Safety - NUTHOS 11, Oct 2016, Gyeongju, South Korea Communication dans un congrès hal-03530213v1
CORE COOLABILITY IN LOSS OF COOLANT ACCIDENT: THE COAL EXPERIMENTS Georges Repetto,Christophe Marquié,Benoit Bruyère,Tony Glantz 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2016, American Nuclear Society, Aug 2015, CHICAGO, United States Communication dans un congrès irsn-04474816v1
Core coolability in loss of coolant accident: the PERFROI project Georges Repetto,Philippe March,Christophe Marquié,Nicolas Waekel,Marie-Christine Baiettoet al. Top Fuel 14, American Nuclear Society, Sep 2014, Sendai (Japan), Japan Communication dans un congrès irsn-04474876v1
New insights in the thermal hydraulics behaviour during reflooding of a high temperature debris bed Georges Repetto,Thierry Garcin,Stephane Eymery 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-15), American Nuclear Society (ANS), May 2013, Pisa, Italy Communication dans un congrès hal-05539851v1
Experimental program on debris reflooding (PEARL) – Results on PRELUDE facility Georges Repetto,Thierry Garcin,Stephane Eymery,Florian Fichot The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), Sep 2011, Toronto, Canada. pp.176-186, ⟨10.1016/j.nucengdes.2012.11.024⟩ Communication dans un congrès hal-05054388v1
Quench front progression in a superheated porous medium: experimental analysis and model development Andrea Bachrata,Florian Fichot,Georges Repetto,Michel Quintard,Joëlle Fleurot NURETH 14 2011 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Sep 2011, Toronto, Canada. pp.0 Communication dans un congrès hal-04028871v1
DRACCAR, a new 3D-thermal mechanical computer code to simulate LOCA transient on Nuclear Power Plants Status of the development and the validation Georges Repetto,Francois Jacq,François Barré,François Lamare,Jean-Marc Ricaud International Congress on Advances in Nuclear Power Plants 2009 (ICAPP 2009), American Nuclear Society (ANS), May 2009, Tokyo, Japan Communication dans un congrès hal-05539789v1
Preliminary Analysis of Phebus FPT3 Experiment with the Severe Accident ICARE2 Code Olivier de Luze,Georges Repetto,Nathalie Seiler,Cristina Dominguez 14th International Conference on Nuclear Engineering (ICONE-14), ASME – American Society of Mechanical Engineers, Jul 2006, Miami, United States. pp.85-94, ⟨10.1115/ICONE14-89191⟩ Communication dans un congrès hal-05539530v1
Application of the Porous Medium Heat transfer model of ICARE/CATHARE code against debris bed and &quot;bundle&quot; &quot; experiments Georges Repetto,Stefano Ederli EUROTHERM Seminar 81 – Computational Thermal Radiation in Participating Media 2007, École des Mines d’Albi-Carmaux (EMAC), Jun 2007, Albi, France Communication dans un congrès hal-05539598v1
Analysis of the FPT-0 and FPT-2 PHEBUS FP experiments using porous medium geometry with the ICARE2 CODE Georges Repetto,Stefano Ederli 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), American Nuclear Society (ANS), Oct 2005, Avignon, France Communication dans un congrès hal-05539816v1
Analyses of the PHEBUS-LOCA tests 215-R and 218 using FRETA-F V1.1 CODE Serge Bourdon,Georges Repetto,Sarah Brethes 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), American Nuclear Society (ANS); Société Française d’Énergie Nucléaire (SFEN), Oct 2005, Avignon, France Communication dans un congrès hal-05540050v1
Analysis of the FPT0, FPT1 and FPT2 experiments of the PHÉBUS FP program investigating in vessel phenomena during a LWR accident Georges Repetto,Bernard Clément,Stefano Ederli 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), American Nuclear Society (ANS), Oct 2003, Séoul, South Korea Communication dans un congrès hal-05539875v1

Poster de conférence (1)

MRI as a tool for nuclear safety Sebastien Leclerc,A V S Oliveira,Didier Stemmelen,T Glantz,Alexandre Labergueet al. Italian-French International Conference on Magnetic Resonance, Sep 2022, Milan, Italy Poster de conférence hal-03798574v1