Jérôme Sercombe Ingénieur chercheur IRESNE

Identifiants chercheurs

IdHAL :

jerome-sercombe

ORCID :

0009-0003-9488-503X

Présentation

Ingénieur chercheur IRESNE

Publications

Communication dans un congrès (26)

Investigation of central hole formation at very high power levels in PWR nuclear fuel by simulations and laser experiments Maxime Gérard,Veronica d'Ambrosi,J. Sercombe,T. Doualle,Yves Pontillonet al. Top Fuel 2024, 2024, Grenobe, France Communication dans un congrès hal-05519727v1
High power Laser-based for nuclear fuels behaviour and properties investigation under extreme conditions Thomas Doualle,Yves Pontillon,Carlos Esteban Cifuentes Quintal,Matthieu Reymond,Christian Colinet al. 8th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2023, Luca, Italy Communication dans un congrès hal-04456882v1
Progress in Modeling Clad Ballooning during the NSRR RIA Tests using ALCYONE Fuel Performance Code I. Guénot-Delahaie,J. Sercombe,R. Largenton,X. Haller TOP FUEL 2022, Oct 2022, Raleigh, United States. pp.650-659, ⟨10.13182/TopFuel22-38886⟩ Communication dans un congrès cea-04652480v1
Laser-based experiments to investigate nuclear fuels behaviour under thermal stresses Thomas Doualle,Matthieu Reymond,Vincent Klosek,Jérôme Sercombe,Laurent Gallaiset al. E-MRS 2022, 2022, En ligne, France Communication dans un congrès hal-03917303v1
Improvement of materials science knowledge for corium and FP, from standpoints of thermodynamics and kinetics Andrea Quaini,Christine Gueneau,Mathieu Garrigue,Clement Introini,Jerome Sercombe TCOFF final Workshop, Dec 2021, Paris, France Communication dans un congrès cea-03672602v1
Modeling of fuel behaviour during RIA transients: new insights gained thanks to laser heating experiments Matthieu Reymond,Thomas Doualle,Laurent Gallais,Sercombe Jérôme,Yves Pontillon Top Fuel, 2021, Santander, Spain Communication dans un congrès hal-03466324v1
PLEIADES ALCYONE 3.5D simulation of a power ramp including OpenCalphad fuelthermochemistry with TAF-ID C. Introini,J. Sercombe,C. Gueneau,P. Goldbronn NuFuel MMSNF, Nov 2019, VILLIGEN, Switzerland Communication dans un congrès cea-02613566v1
PLEIADES ALCYONE 3.5D simulation of a power ramp including OpenCalphad fuelthermochemistry with TAF-ID C. Introïni,J. Sercombe,C. Gueneau,P. Goldbronn NuFuel MMSNF workshop, Nov 2019, Villigen, Switzerland Communication dans un congrès cea-02614121v1
PLEIADES ALCYONE 3.5D simulation of a power ramp including OpenCalphad fuelthermochemistry with TAF-ID C. Introini,J. Sercombe,C. Gueneau,P. Goldbronn NuFuel MMSNF, Nov 2019, VILLIGEN, Switzerland Communication dans un congrès cea-02613616v1
Integration of OpenCalphad thermo-chemical solver in PLEIADES/ALCYONE fuel performance code C. Introini,J. Sercombe,J.-C. Dumas,P. Goldbronn,V. Marelle NUMAT 2018 - The Nuclear Materials Conference 2018, Oct 2018, Seattle, United States Communication dans un congrès cea-02339455v1
Speciation and release kinetics of the fission products Mo, Cs, Ba and I from nuclear fuels in severe accident conditions Ch. Riglet-Martial,J. Sercombe,Yves Pontillon WRFPM 2018, Sep 2018, Prague, Czech Republic Communication dans un congrès cea-02400191v1
Simulation of RIA transients on MOX fuel rods with ALCYONE fuel performance code I. Guenot-Delahaie,Jérôme Sercombe,Antoine Bouloré,Eric Federici,Rodrigue Largentonet al. TopFuel2018 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Prague, Czech Republic Communication dans un congrès cea-02338540v1
3D simulation of a power ramp including oxygen thermo-diffusion and its impact on thermochemistry P. Konarski,J. Sercombe,C. Riglet-Martial,I. Zacharie-Aubrun,M. Fregoneseet al. TOPFUEL 2018 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Prague, Czech Republic Communication dans un congrès cea-02400207v1
SIMULATION OF RIA TRANSIENTS ON MOX FUEL RODS WITH ALCYONE FUEL PERFORMANCE CODE I Guénot-Delahaie,J. Sercombe,A Bouloré,É Fédérici,R Largentonet al. TopFuel 2018 Reactor Fuel Performance Meeting, Sep 2018, Prague, Czech Republic Communication dans un congrès hal-01889141v1
SIMULATION OF RIA TRANSIENTS ON UO2 -M5® FUEL RODS WITH ALCYONE V1.4 FUEL PERFORMANCE CODE I Guénot-Delahaie,J. Sercombe,T Helfer,P Goldbronn,É Fédériciet al. WRFPM 2017, Sep 2017, JEJU Island, South Korea Communication dans un congrès hal-01860413v1
Simulation of RIA transients on UO2-M5 fuel rods with ALCYONE v1.4 Fuel performance code J. Sercombe,T. Helfer,P. Goldbronn,E. Federici,T. Le Joluet al. WRFPM 2017 (TOPFUEL), Sep 2017, Jeju-do, South Korea Communication dans un congrès hal-02417383v1
simulation of ria transients on uo2-m5 fuel rodswith alcyone v1.4 fuel performance code I. Guenot-Delahaie,J. Sercombe,T. Helfer,P. Goldbronn,E. Federiciet al. WRFPM 2017 Water Reactor Fuel Performance Meeting, Sep 2017, Jeju Island, South Korea Communication dans un congrès hal-02433897v1
3d thermo-chemical-mechanical simulation of power ramps with alcyone fuel code B. Baurens,J. Sercombe,C. Riglet-Martial,L. Desgranges,L. Trotignonet al. Top Fuel 2015, Sep 2015, Zurich, Switzerland Communication dans un congrès cea-02509262v1
Recent improvements of the thermomechanical modeling in the PLEIADES platform applications to the simulation of PWR accidental transient conditions using the Alcyone fuel performance code T. Helfer,J. Sercombe,B. Michel,I. Ramiere,M. Salvoet al. MMSNF-Nufuel, Nov 2015, Karlsruhe, Germany Communication dans un congrès hal-02416330v1
2D simulations of hydride blister cracking during a RIA transient with the fuel code ALCYONE J. Sercombe,T. Helfer,E. Federici,D. Leboulch,T. Le Joluet al. Top Fuel 2015, Sep 2015, Zurich, Switzerland Communication dans un congrès cea-02500835v1
1D and 2D analyses of the IFA-610 lift-off experiments with the fuel code ALCYONE C. Bassi,J. Sercombe,B. Petitprez EHPG 2014 - the 41st in the series of Enlarged Halden Programme Group meetings, Sep 2014, RØros, Norway Communication dans un congrès cea-02874737v1
Comportement mécanique en compression du dioxyde d'Uranium à température élevée et haute vitesse de sollicitation Maxime Salvo,Jérôme Sercombe,Jean-Claude Menard,Jean-Pierre Alessandri,Thierry Desoyer CFM 2013 - 21ème Congrès Français de Mécanique, Aug 2013, Bordeaux, France Communication dans un congrès hal-03441360v1
Avancées de la simulation du comportement du combustible nucléaire en 3D et en transitoire rapide Patrick Goldbronn,Jérôme Sercombe,Bruno Michel CFM 2013 - 21ème Congrès Français de Mécanique, Aug 2013, Bordeaux, France Communication dans un congrès hal-03441407v1
Experimental characterization of the mechanical behavior in compression of uranium dioxide at high strain rate Salvo Maxime,Sercombe Jérôme,Jean-Claude Ménard,Alessandri Jean-Pierre,Thierry Désoyer 21ème Congrès Français de Mécanique, Aug 2013, Bordeaux, France Communication dans un congrès cea-03306703v1
AMR Methods in solids mechanics for pellet-cladding interaction modelling Laureline Barbié,Isabelle Ramière,Frédéric Lebon,Jérôme Sercombe 5th International Conference on Adaptative Modeling and Simulation ADMOS 2011, Jun 2011, Paris, France Communication dans un congrès hal-00589998v1
1D and 3D modelling of PCMI during a RIA with ALCYONE v1.1 Jérôme Sercombe,Éric Fédérici,Matthieu Le Saux,Bruno Michel,Christophe Poussard International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2010, Orlando, United States. pp.307-318 Communication dans un congrès hal-04447310v1

Article dans une revue (36)

Fission products at the fuel-cladding interface of PWR fuel rods: morphological and chemical study C. Schneider,L. Fayette,I. Zacharie-Aubrun,T. Blay,C. Onofri-Marroncleet al. Journal of Nuclear Materials, 2023, 585, pp.154600. ⟨10.1016/j.jnucmat.2023.154600⟩ Article dans une revue (article de synthèse) hal-04276119v1
P2M Simulation Exercise on past fuel melting irradiation experiments V. D’ambrosi,J. Sercombe,S. Bejaoui,A. Chaieb,B. Baurenset al. Nuclear Technology, 2023, 210 (2), pp.189-215. ⟨10.1080/00295450.2023.2194270⟩ Article dans une revue cea-04652865v1
Presentation of the xM3 test case of the P2M simulation exercise and modeling with the fuel performance code ALCYONE V. D’ambrosi,J. Sercombe,S. Béjaoui,I. Zacharie-Aubrun,C. Introïniet al. Nuclear Technology, 2023, 210 (2), pp.285-307. ⟨10.1080/00295450.2023.2253660⟩ Article dans une revue cea-04652862v1
2D(r,θ) simulations of the HBC-4 power-to-melt experiment with the fuel performance code ALCYONE J. Sercombe,V. D’ambrosi,S. Béjaoui,I. Zacharie-Aubrun Nuclear Technology, 2023, 210 (2), pp.269-284. ⟨10.1080/00295450.2023.2188138⟩ Article dans une revue cea-04652640v1
High power laser heating of nuclear ceramics for the generation of controlled spatiotemporal gradients Matthieu Reymond,Thomas Doualle,Jerome Sercombe,Mathilde Rocca,Mehdi Nasselahsenet al. Journal of Applied Physics, 2023, 134 (3), pp.033101. ⟨10.1063/5.0146541⟩ Article dans une revue hal-04412911v1
Study of the hardness and Young's modulus at the fuel-cladding interface of a high-burnup PWR fuel rod by nanoindentation measurements C. Schneider,L. Fayette,I. Zacharie-Aubrun,T. Blay,J. Sercombeet al. Journal of Nuclear Materials, 2022, 560, pp.153511. ⟨10.1016/j.jnucmat.2022.153511⟩ Article dans une revue (article de synthèse) hal-04276169v1
Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests A. Germain,J. Sercombe,C. Riglet-Martial,C. Introïni,L. Noirotet al. Journal of Nuclear Materials, 2022, 561, pp.153527. ⟨10.1016/j.jnucmat.2022.153527⟩ Article dans une revue hal-04018896v1
Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents A. Germain,J. Sercombe,C. Riglet-Martial,C. Introïni,L. Noirotet al. Journal of Nuclear Materials, 2022, 560, pp.153429. ⟨10.1016/j.jnucmat.2021.153429⟩ Article dans une revue hal-04018893v1
Investigation of clad ballooning during NSRR RIA tests using ALCYONE fuel performance code Isabelle Guenot-Delahaie,Jerome Sercombe,Eric Federici,Christian Bernaudat,Rodrigue Largentonet al. Journal of Nuclear Materials, 2022, 562, pp.153584. ⟨10.1016/j.jnucmat.2022.153584⟩ Article dans une revue cea-03713987v1
Modeling of fission product release during severe accidents with the fuel performance code ALCYONE A. Germain,J. Sercombe,C. Riglet-Martial,C. Introïni,L. Noirotet al. Nuclear Engineering and Design, 2022, 393, pp.111778. ⟨10.1016/j.nucengdes.2022.111778⟩ Article dans une revue hal-04018889v1
Thermo-mechanical simulations of laser heating experiments on UO$_2$ Matthieu Reymond,Jerome Sercombe,Laurent Gallais,Thomas Doualle,Yves Pontillon Journal of Nuclear Materials, 2021, 557, pp.153220. ⟨10.1016/j.jnucmat.2021.153220⟩ Article dans une revue hal-03466237v1
Microstructural Analysis of Zirconia at the Fuel-Cladding Interface in Medium and High Burnup Irradiated Fuel Rods C. Schneider,L. Fayette,I. Zacharie-Aubrun,T. Blay,J. Sercombeet al. Oxidation of Metals, 2021, 96 (3-4), pp.295-306. ⟨10.1007/s11085-021-10045-8⟩ Article dans une revue hal-04276172v1
Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients Clément Introïni,Jérôme Sercombe,Isabelle Ramière,Romain Le Tellier Journal of Nuclear Materials, 2021, 556, pp.153173. ⟨10.1016/j.jnucmat.2021.153173⟩ Article dans une revue cea-03581220v1
Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1 fuel performance code and the OpenCalphad thermo-chemical solver C. Introïni,J. Sercombe,Bo Sundman Nuclear Engineering and Design, 2020, 369, pp.110818. ⟨10.1016/j.nucengdes.2020.110818⟩ Article dans une revue cea-04652986v1
Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating Thierry Vidal,L. Gallais,J. Faucheux,H. Capdevila,J. Sercombeet al. Journal of Nuclear Materials, 2020, 530 (13), pp.151944. ⟨10.1016/j.jnucmat.2019.151944⟩ Article dans une revue hal-02426429v1
3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion P. Konarski,J. Sercombe,C. Riglet-Martial,L. Noirot,I. Zacharie-Aubrunet al. Journal of Nuclear Materials, 2019, 519, pp.104-120. ⟨10.1016/j.jnucmat.2019.03.021⟩ Article dans une revue hal-02405439v1
Simulation of reactivity-initiated accident transients on UO2 -M5® fuel rods with ALCYONE V1.4 fuel performance code Isabelle Guénot-Delahaie,Jérôme Sercombe,Thomas Helfer,Patrick Goldbronn,Éric Fédériciet al. Nuclear Engineering and Technology, 2018, 50 (2), pp.268 - 279. ⟨10.1016/j.net.2017.12.006⟩ Article dans une revue hal-01860402v1
Simulation of Pellet-Cladding interaction with the PLEIADES fuel performance software environment B. Michel,C. Nonon,J. Sercombe,F. Michel,V. Marelle Nuclear Technology, 2017, 182 (2), pp.124-137. ⟨10.13182/NT13-A16424⟩ Article dans une revue hal-04060973v1
Experimental Evidence of Oxygen Thermo-Migration in PWR UO$_2$ Fuels during Power Ramps using In-situ Oxido-Reduction Indicators C. Riglet Martial,J. Sercombe,J. Lamontagne,J. Noirot,I. Roureet al. Journal of Nuclear Materials, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩ Article dans une revue cea-02389290v1
2D simulation of hydride blister cracking during a RIA transient with the fuel code ALCYONE Jérôme Sercombe,Thomas Helfer,Eric Federici,David Leboulch,Thomas Le Joluet al. EPJ N - Nuclear Sciences & Technologies, 2016, 2, pp.22. ⟨10.1051/epjn/2016016⟩ Article dans une revue cea-01350715v1
Introducing the open-source mfront code generator: Application to mechanical behaviours and material knowledge management within the PLEIADES fuel element modelling platform Thomas Helfer,Bruno Michel,Jean-Michel Proix,Maxime Salvo,Jérôme Sercombeet al. Computers & Mathematics with Applications, 2015, 70 (5), pp.994-1023. ⟨10.1016/j.camwa.2015.06.027⟩ Article dans une revue cea-03306589v1
Experimental characterization and modelling of UO$_2$ grain boundary cracking at high temperatures and high strain rates Salvo Maxime,Jérôme Sercombe,Thomas Helfer,Philippe Sornay,Thierry Désoyer Journal of Nuclear Materials, 2015, 460, pp.184-199. ⟨10.1016/j.jnucmat.2015.02.018⟩ Article dans une revue hal-01199597v1
Experimental and numerical study of fracture mechanisms in UO2 nuclear fuel J.-M. Gatt,J. Sercombe,I. Aubrun,J.-C. Ménard Engineering Failure Analysis, 2015, 47, pp.299-311. ⟨10.1016/j.engfailanal.2014.07.019⟩ Article dans une revue hal-04825110v1
Thermomechanical loading applied on the cladding tube during the pellet cladding mechanical interaction phase of a rapid reactivity initiated accident Arthur Hellouin de Menibus,Jérôme Sercombe,Quentin Auzoux,Christophe Poussard Journal of Nuclear Materials, 2014, 453, pp.210-213. ⟨10.1016/j.jnucmat.2014.06.046⟩ Article dans une revue hal-01057281v1
Experimental characterization and modelling of UO2 behavior at high temperatures and high strain rates Maxime Salvo,Sercombe Jérôme,Jean-Claude Ménard,Jérôme Julien,Thomas Helferet al. Journal of Nuclear Materials, 2014, Volume 456, pp 54-67. ⟨10.1016/j.jnucmat.2014.09.024⟩ Article dans une revue hal-01199576v1
L’Interaction Pastille-Gaine (IPG) : les phénomènes physiques mis en jeu et les avancées récentes E. Fédérici,J. Sercombe Revue Générale Nucléaire, 2014, 6, pp.61-66. ⟨10.1051/rgn/20136061⟩ Article dans une revue cea-04652852v1
Stress concentration during pellet cladding interaction: Comparison of closed-form solutions with 2D(r,θ) finite element simulations Jérôme Sercombe,Renaud Masson,Thomas Helfer Nuclear Engineering and Design, 2013, 260, pp.175-187. ⟨10.1016/j.nucengdes.2013.03.019⟩ Article dans une revue hal-03427490v1
Power ramped cladding stresses and strains in 3D simulations with burnup-dependent pellet-clad friction J. Sercombe,I. Aubrun,C. Nonon Nuclear Engineering and Design, 2012, 242, pp.164-181. ⟨10.1016/j.nucengdes.2011.08.069⟩ Article dans une revue cea-04652972v1
3D fuel cracking modelling in pellet cladding mechanical interaction B. Michel,J. Sercombe,G. Thouvenin,R. Chatelet Engineering Fracture Mechanics, 2008, 75 (11), pp.3581-3598. ⟨10.1016/j.engfracmech.2006.12.014⟩ Article dans une revue istex cea-02093543v1
A new phenomenological criterion for pellet-cladding interaction rupture B. Michel,J. Sercombe,G. Thouvenin Nuclear Engineering and Design, 2008, 238 (7), pp.1612-1628. ⟨10.1016/j.nucengdes.2008.01.012⟩ Article dans une revue cea-02514885v1
Modelling of radionuclide release from a concrete container S. Bejaoui,Jérôme Sercombe,Claude Mugler,Hugues Peycelon Transport in Porous Media, 2007, 69 (1), pp.89-107. ⟨10.1007/s11242-006-9066-3⟩ Article dans une revue istex hal-02887343v1
Long-term performance of cement paste during a combined calcium leaching-sulfate attack. Kinetics and size effects D. Planel,J. Sercombe,H. Peycelon,P. Le Bescop,F. Adenotet al. Cement and Concrete Research, 2006, 36, pp.137-143 Article dans une revue hal-00119809v1
Modelling of bituminized radioactive waste leaching. Part II: Experimental validation B. Gwinner,J. Sercombe,C. Tiffreau,B. Simondi-Teisseire,I. Felineset al. Journal of Nuclear Materials, 2006, 349 (1-2), pp.107-118. ⟨10.1016/j.jnucmat.2005.10.019⟩ Article dans une revue istex hal-03018229v1
Experimental study of gas diffusion in cement paste J. Sercombe,R. Vidal,C. Galle,F. Adenot Cement and Concrete Research, 2006, 37 (4), pp.579-588. ⟨10.1016/j.cemconres.2006.12.003⟩ Article dans une revue cea-02360113v1
Modelling of bituminized radioactive waste leaching. Part I: Constitutive equations J. Sercombe,B. Gwinner,C. Tiffreau,B. Simondi-Teisseire,F. Adenot Journal of Nuclear Materials, 2006, 349 (1-2), pp.96-106. ⟨10.1016/j.jnucmat.2005.10.014⟩ Article dans une revue istex hal-03018230v1
Stockage en profondeur des déchets nucléaires bitumés B. Gwinner,J. Sercombe,B. Simondi-Teisseire,I. Felines,C. Tiffreauet al. Environnement, Ingénierie & Développement, 2004, N°36 - 4ème Trimestre 2004, pp.13-18. ⟨10.4267/dechets-sciences-techniques.2141⟩ Article dans une revue hal-03176881v1

Chapitre d'ouvrage (2)

Two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL Bruno Michel,Isabelle Ramière,Isabelle Viallard,Clément Introini,Marc Lainetet al. Nuclear Power Plant Design and Analysis Codes, Elsevier, pp.207-233, 2021, ⟨10.1016/B978-0-12-818190-4.00009-7⟩ Chapitre d'ouvrage cea-03581238v1
Modeling of pellet cladding interaction Jerome Sercombe,Bruno Michel,Chantal Riglet-Martial,Olivier. Fandeur Rudy J.M. Konings; Roger E. Stoller. Comprehensive Nuclear Materials - Second Edition. Volume 2 : Oxide Fuel Systems in Thermal and Fast Neutron Spectrum Reactors, 2 (2.14), Elsevier, 2020, 978-0-08-102866-7. ⟨10.1016/B978-0-12-803581-8.00715-3⟩ Chapitre d'ouvrage hal-04825099v1