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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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 zinc21st 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
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On the progress made in safety assessment and severe accident management as part of the french Fukushima post-accident research programmeThe 11th European Review Meeting on Severe Accident Research (ERMSAR2024), Königlich Technische Hochschule Stockholm (KTH), May 2024, Stockholm, Sweden
Communication dans un congrès
irsn-04858131
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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 rods20th 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
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Coal experiments investigating the reflooding of a 7 x 7 rods bundle during a loss of coolant accident thermalhydraulics resultsThe 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
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Simulation de l'écoulement dispersé vapeur/gouttes dans des conditions d'APRP29e Congrès français de thermique, Société Française de Thermique, Jun 2021, Belfort, France. ⟨10.25855/SFT2021-037⟩
Communication dans un congrès
hal-03529904
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Operation Extension of 900MWe NPPs: French TSO Main Conclusions regarding Long Term Sump Performance after a Loss of Coolant AccidentRCCS - 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
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VIKTORIA experiments on sump filtration during a Loss Of Coolant Accident (DBA)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
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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 effects18th 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
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Analyse des transferts thermiques d'un écoulement vertical vapeur/gouttes dans une géométrie tubulaire27e Congrès français de thermique, Jun 2019, Nantes, France
Communication dans un congrès
hal-03529839
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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 evolutionNURETH 2019 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, PORTLAND, United States. pp.407-420
Communication dans un congrès
irsn-04111911
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Identification des transferts thermiques d'un écoulement vertical vapeur/gouttes dans une géométrie tubulaireCongrès français de thermique, May 2018, Pau, France
Communication dans un congrès
hal-03529820
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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 REFLOODING2017 International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), American Nuclear Society, Sep 2017, Xi’an, China
Communication dans un congrès
irsn-04474794
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CoreSOAR Core Degradation SOAR Update Status May 20178th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland
Communication dans un congrès
hal-02418127
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Heat transfer inside a blocked region of a rod bundle during a LOCA-simulations and experiments9th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics (EXHFT-9), Jun 2017, Iguazu, Brazil
Communication dans un congrès
hal-03530191
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Study on Heat Transfer Inside a Blocked Region of a Rod Bundle During a LOCA - Model and Experimental Approach17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-17, Sep 2017, Xian, China
Communication dans un congrès
hal-03530147
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Experimental study on heat transfer inside a blocked region of a rod bundle during a LOCA11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operations and Safety - NUTHOS 11, Oct 2016, Gyeongju, South Korea
Communication dans un congrès
hal-03530213
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Thermal hydraulics behavior of a rod bundle with partially blocked area during the reflooding phase of the Loss Of Cooling AccidentNUTHOS-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
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CORE COOLABILITY IN LOSS OF COOLANT ACCIDENT: THE COAL EXPERIMENTS16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2016, American Nuclear Society, Aug 2015, CHICAGO, United States
Communication dans un congrès
irsn-04474816
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Core coolability in loss of coolant accident: the PERFROI projectTop Fuel 14, American Nuclear Society, Sep 2014, Sendai (Japan), Japan
Communication dans un congrès
irsn-04474876
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Experimental program on debris reflooding (PEARL) – Results on PRELUDE facilityThe 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
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Quench front progression in a superheated porous medium: experimental analysis and model developmentNURETH 14 2011 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Sep 2011, Toronto, Canada. pp.0
Communication dans un congrès
hal-04028871
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MRI as a tool for nuclear safetyItalian-French International Conference on Magnetic Resonance, Sep 2022, Milan, Italy
Poster de conférence
hal-03798574
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