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Les accidents de fusion du cœur des réacteurs nucléaires de puissance

Ahmed Bentaïb , Hervé Bonneville , Gerard Cenerino , Bernard Clément , François Corenwinder , et al.
IRSN. EDP sciences, pp.1-444, 2013, Collection sciences et techniques, Odile Lefèvre, 978-2-7598-0972-1
Ouvrages irsn-04256450v1
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Modélisation de la dissolution d'une phase solide (UO2-ZrO2-Zr) par une phase liquide (Fe) par une approche macroscopique diphasique

Shambhavi Nandan
Mécanique des fluides [physics.class-ph]. Aix-Marseille Université, 2019. Français. ⟨NNT : 2019AIXM0663⟩
Thèse tel-04393909v1
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Etude expérimentale de l'ébullition convective en milieu poreux : assèchement et flux critique

Ange Gourbil
Mécanique des fluides [physics.class-ph]. Institut National Polytechnique de Toulouse - INPT, 2017. Français. ⟨NNT : 2017INPT0053⟩
Thèse tel-04222853v1
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Étude expérimentale et modélisation cinétique de l'oxydation à haute température sous air et vapeur d'eau du Zircaloy-4 pré-oxydé.

Mathilde Gestin
Autre. Université de Lyon, 2019. Français. ⟨NNT : 2019LYSEM002⟩
Thèse tel-03534233v1
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Coolability of a Corium Pool in a Debris Bed -Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

C. Sartoris , T. Garcin , F. Fichot
NURETH-20, Aug 2023, Washington DC, United States
Communication dans un congrès irsn-04112787v1

Calculating steam-water flows at large non-condensible gas concentration with severe accident code astec v2.2

Julie Anne Zambaux , Laurent Laborde , Pierre Ruyer
19TH INTERNATIONAL TOPICAL MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS, NURETH, Mar 2022, BRUXELLES, Belgium
Communication dans un congrès hal-03658405v1
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Development of a new steam explosion model for the MC3D software

Linkai Wei
Reactive fluid environment. Université de Lorraine, 2023. English. ⟨NNT : 2023LORR0097⟩
Thèse tel-04216777v1
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Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Sara Perez-Martin , Marine Anderhuber , Laurent Laborde , Nathalie Girault , Calogera Lombardo , et al.
Journal of Nuclear Engineering and Radiation Science, 2021, 8 (1), ⟨10.1115/1.4050769⟩
Article dans une revue irsn-04112113v1
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Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions

Stefano Ederli , Patrick Drai , Dorel Obada , Nathalie Girault , Fulvio Mascari
Annals of Nuclear Energy, 2024, Annals of Nuclear Energy vol 203, 203, pp.11053. ⟨10.1016/j.anucene.2024.110503⟩
Article dans une revue irsn-04616437v1

Analysis and modeling of ex-vessel underwater cooling processes of debris bed and molten corium pool in interaction with concrete

Alejandro Villarreal Larrauri
Reactive fluid environment. Université de Lorraine, 2020. English. ⟨NNT : 2020LORR0022⟩
Thèse tel-02881112v1

Comparative analysis of core degradation models Between astec and melcor. Application to the Fukushima daiichi unit-1 like accident

Charlaine Bouillet , Patrick Drai , Hervé Bonneville , Vincent Topin , Laurent Laborde , et al.
NURETH18 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, Portland, United States
Communication dans un congrès irsn-04106707v1
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Synthesis of the ASTEC V2.2 code validation vs. experimental data

Patrick Chatelard , Laurent Laborde
The 10th European Review Meeting on Severe Accident Research (ERMSAR-2022), ERMSAR, 2022, KARLSRUHE, Germany
Communication dans un congrès hal-03677729v1
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Main outcomes from the IVR code benchmark performed in the IVMR European project

Laure Carénini , Florian Fichot , Nikolai Bakouta , Aleksandr Filippov , Romain Le Tellier , et al.
Annals of Nuclear Energy, 2020, 146, pp.107612. ⟨10.1016/j.anucene.2020.107612⟩
Article dans une revue hal-03490651v1
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A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Haileyesus Tsige-Tamirat , Sara Perez-Martin , Werner Pfrang , Marine Anderhuber , Antoine Gerschenfeld , et al.
Journal of Nuclear Engineering and Radiation Science, 2022, 8 (1), pp.011305. ⟨10.1115/1.4051066⟩
Article dans une revue irsn-04111893v1
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ASTEC V2.2 code validation: Illustrative results and main outcomes

Patrick Chatelard , Laurent Laborde
Nuclear Engineering and Design, 2023, 413, pp.112547. ⟨10.1016/j.nucengdes.2023.112547⟩
Article dans une revue irsn-04195835v1
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Reflooding of degraded cores in ASTEC V2.1: modelling and validation on PEARL experiments

Ignacio Gómez-García-Toraño , Laurent Laborde , Florian Fichot , Hervé Mutelle
Nuclear Engineering and Design, 2022, 393, pp.111768. ⟨10.1016/j.nucengdes.2022.111768⟩
Article dans une revue hal-03863989v1
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Elaboration of a phenomena identification ranking table (PIRT) for the modelling of In-Vessel Retention

F. Fichot , L. Carénini , N. Bakouta , H. Esmaili , L. Humphries , et al.
Annals of Nuclear Energy, 2020, 146, pp.107617. ⟨10.1016/j.anucene.2020.107617⟩
Article dans une revue hal-03490652v1
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Etude expérimentale de l'ébullition en masse dans un milieu poreux modèle

Paul Sapin
Mécanique des fluides [physics.class-ph]. Institut National Polytechnique de Toulouse - INPT, 2014. Français. ⟨NNT : 2014INPT0043⟩
Thèse tel-04262100v1

Characterization of magma flows through a debris bed during a severe accident

Juliana Garcia Sarmiento
Fluids mechanics [physics.class-ph]. Aix-Marseille Université, 2022. English. ⟨NNT : 2022AIXM0445⟩
Thèse tel-04441897v1
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Interaction between forced and natural convection in a thin cylindrical fluid layer at low Prandtl number

F. Rein , Laure Carénini , Florian Fichot , B. Favier , M. Le Bars
Journal of Fluid Mechanics, 2023, 977, pp.A26. ⟨10.1017/jfm.2023.922⟩
Article dans une revue hal-04380002v1
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Main outcomes from the IVR code benchmark performed in the IVMR project

Laure Carénini , Florian Fichot , Nikolai Bakouta , Aleksandr Filippov , Romain Le Tellier , et al.
9th Conference on Severe Accident Research (ERMSAR 2019), UJV REZ, Mar 2019, Prague, Czech Republic. pp.107612, ⟨10.1016/j.anucene.2020.107612⟩
Communication dans un congrès irsn-04115899v1
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Oxidation during fuel-coolant interaction Advances and modeling

V. Loisel , J.-A. Zambaux , M. Hadj-Achour , S. Picchi , O. Coindreau , et al.
Nuclear Engineering and Design, 2019, 346, pp.200-208. ⟨10.1016/j.nucengdes.2019.02.008⟩
Article dans une revue hal-02524205v1
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Coolability of a corium pool in a debris bed – Critical heat flux (CHF) dependency with tilting angle, debris size and steam flowrate

C. Sartoris , Thierry Garcin , Florian Fichot
Nuclear Engineering and Design, 2023, 403, pp.112146. ⟨10.1016/j.nucengdes.2022.112146⟩
Article dans une revue irsn-04112431v1

Pore-scale experimental study of boiling in porous media

Paul Sapin , Paul Duru , Florian Fichot , Marc Prat , Michel Quintard
International Heat Transfer Conference 15, IHTC Digital Library, pp.6111-6124, 2014, 978-1-56700-421-2. ⟨10.1615/IHTC15.pbl.009914⟩
Proceedings/Recueil des communications hal-04466128v1
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Modelling reflooding of intact core geometries in ASTEC V2.1: Improvements and validation on PERICLES experiments

Laurent Laborde , Ignacio Gomez Garcia Torano
Nuclear Engineering and Design, 2021, 378, pp.111157. ⟨10.1016/j.nucengdes.2021.111157⟩
Article dans une revue hal-03375548v1
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BEPU analysis of a 2-in DVI break in a generic IRIS SMR by ASTEC -RAVEN coupling

Pietro Maccari , Julie Anne Zambaux , Andrea Bersano
Eurosafe 2021 - Nuclear and radiation safety in a disruptive world, ETSON, Nov 2021, Montrouge, France
Communication dans un congrès irsn-04111904v1
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Interfacial heat transfer with non-condensable gas in ASTEC V2.2: Application to severe accidents study during PWR cold shutdown states

Julie-Anne Zambaux , Laurent Laborde
Nuclear Engineering and Design, 2023, 411, pp.112434. ⟨10.1016/j.nucengdes.2023.112434⟩
Article dans une revue irsn-04130158v1
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Experimental study of boiling in porous media

Paul Sapin , Paul Duru , Florian Fichot , Marc Prat , Michel Quintard
ASME 2013 Heat Transfer Summer Conference, Jul 2013, Minneapolis, United States. pp.0
Communication dans un congrès hal-04086559v1

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO2 Pool in Natural Convection

Claude Jamond , Elena Martin Lopez , Xue-Nong Chen , Nathalie Girault , Pierre Gubernatis , et al.
Journal of Nuclear Engineering and Radiation Science, 2022, 8 (1), ⟨10.1115/1.4052489⟩
Article dans une revue irsn-03647516v1