Georges REPETTO

Chef de projet
33
Documents
Affiliation actuelle
  • Service de l'Ingénierie et des Projets de Recherche (IRSN/PSN-RES/SIPR)

Publications

Publications

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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-05086681 v1
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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-04879532 v1

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-04738309 v1
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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-04751843 v1
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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 Labergue et al.
Experimental Thermal and Fluid Science, 2021, 125, pp.110383. ⟨10.1016/j.expthermflusci.2021.110383⟩
Article dans une revue hal-03162585 v1
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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 Labergue et al.
Nuclear Engineering and Design, 2020, 369, pp.110828. ⟨10.1016/j.nucengdes.2020.110828⟩
Article dans une revue hal-02940079 v1

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-03113377 v1
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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-04312479 v1

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-03111570 v1

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. Hollands et al.
Nuclear Technology, 2011, 176 (3), pp.352--371. ⟨10.13182/NT11-A13313⟩
Article dans une revue hal-02962929 v1

B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments

G. Repetto , O. de Luze , N. Seiler , K. Trambauer , H. Austregesilo et al.
Progress in Nuclear Energy, 2010, 52 (1), pp.37-45. ⟨10.1016/j.pnucene.2009.09.017⟩
Article dans une revue istex hal-02972637 v1
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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-05497002 v1
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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-04858131 v1
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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. Fortman et 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-04200520 v1
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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-04100311 v1
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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 Repetto et al.
29e Congrès français de thermique, Société Française de Thermique, Jun 2021, Belfort, France. ⟨10.25855/SFT2021-037⟩
Communication dans un congrès hal-03529904 v1
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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-04113763 v1
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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-04113818 v1
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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-04113583 v1
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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 Repetto et al.
27e Congrès français de thermique, Jun 2019, Nantes, France
Communication dans un congrès hal-03529839 v1
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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-04111911 v1
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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-03529820 v1
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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-04474794 v1
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CoreSOAR Core Degradation SOAR Update Status May 2017

T. Haste , M. Barrachin , F. Fichot , G. Repetto , A. Miassoedov et al.
8th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland
Communication dans un congrès hal-02418127 v1
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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-03530191 v1
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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-03530147 v1
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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-03530213 v1
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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-04474648 v1
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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-04474816 v1
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Core coolability in loss of coolant accident: the PERFROI project

Georges Repetto , Philippe March , Christophe Marquié , Nicolas Waekel , Marie-Christine Baietto et al.
Top Fuel 14, American Nuclear Society, Sep 2014, Sendai (Japan), Japan
Communication dans un congrès irsn-04474876 v1

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-05054388 v1
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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-04028871 v1
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MRI as a tool for nuclear safety

Sebastien Leclerc , A V S Oliveira , Didier Stemmelen , T Glantz , Alexandre Labergue et al.
Italian-French International Conference on Magnetic Resonance, Sep 2022, Milan, Italy
Poster de conférence hal-03798574 v1