Jérôme Sercombe

Ingénieur chercheur IRESNE
71%
Libre accès
63
Documents
Affiliation actuelle
  • Département d'Etudes des Combustibles (DEC)
Identifiants chercheurs

Présentation

Ingénieur chercheur IRESNE

Domaines de recherche

Matériaux et structures en mécanique [physics.class-ph]

Compétences

Combustibles nucléaires

Publications

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Publications

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-Marroncle et al.
Journal of Nuclear Materials, 2023, 585, pp.154600. ⟨10.1016/j.jnucmat.2023.154600⟩
Article dans une revue (article de synthèse) hal-04276119 v1

P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments

V. D’ambrosi , J. Sercombe , S. Bejaoui , A. Chaieb , B. Baurens et al.
Nuclear Technology, 2023, 210 (2), pp.189-215. ⟨10.1080/00295450.2023.2194270⟩
Article dans une revue cea-04652865 v1
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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-04652640 v1

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. Introïni et al.
Nuclear Technology, 2023, 210 (2), pp.285-307. ⟨10.1080/00295450.2023.2253660⟩
Article dans une revue cea-04652862 v1
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High power laser heating of nuclear ceramics for the generation of controlled spatiotemporal gradients

Matthieu Reymond , Thomas Doualle , Jerome Sercombe , Mathilde Rocca , Mehdi Nasselahsen et al.
Journal of Applied Physics, 2023, 134 (3), pp.033101. ⟨10.1063/5.0146541⟩
Article dans une revue hal-04412911 v1
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Investigation of clad ballooning during NSRR RIA tests using ALCYONE fuel performance code

Isabelle Guenot-Delahaie , Jerome Sercombe , Eric Federici , Christian Bernaudat , Rodrigue Largenton et al.
Journal of Nuclear Materials, 2022, 562, pp.153584. ⟨10.1016/j.jnucmat.2022.153584⟩
Article dans une revue cea-03713987 v1
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Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents

A. Germain , J. Sercombe , C. Riglet-Martial , C. Introïni , L. Noirot et al.
Journal of Nuclear Materials, 2022, 560, pp.153429. ⟨10.1016/j.jnucmat.2021.153429⟩
Article dans une revue hal-04018893 v1
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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. Noirot et al.
Journal of Nuclear Materials, 2022, 561, pp.153527. ⟨10.1016/j.jnucmat.2022.153527⟩
Article dans une revue hal-04018896 v1

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. Sercombe et al.
Journal of Nuclear Materials, 2022, 560, pp.153511. ⟨10.1016/j.jnucmat.2022.153511⟩
Article dans une revue (article de synthèse) hal-04276169 v1
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Modeling of fission product release during severe accidents with the fuel performance code ALCYONE

A. Germain , J. Sercombe , C. Riglet-Martial , C. Introïni , L. Noirot et al.
Nuclear Engineering and Design, 2022, 393, pp.111778. ⟨10.1016/j.nucengdes.2022.111778⟩
Article dans une revue hal-04018889 v1
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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-03466237 v1

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. Sercombe et al.
Oxidation of Metals, 2021, 96 (3-4), pp.295-306. ⟨10.1007/s11085-021-10045-8⟩
Article dans une revue hal-04276172 v1
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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-03581220 v1
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Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating

Thierry Vidal , L. Gallais , J. Faucheux , H. Capdevila , J. Sercombe et al.
Journal of Nuclear Materials, 2020, 530 (13), pp.151944. ⟨10.1016/j.jnucmat.2019.151944⟩
Article dans une revue hal-02426429 v1

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-04652986 v1
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3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion

P. Konarski , J. Sercombe , C. Riglet-Martial , L. Noirot , I. Zacharie-Aubrun et al.
Journal of Nuclear Materials, 2019, 519, pp.104-120. ⟨10.1016/j.jnucmat.2019.03.021⟩
Article dans une revue hal-02405439 v1
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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 Fédérici et al.
Nuclear Engineering and Technology, 2018, 50 (2), pp.268 - 279. ⟨10.1016/j.net.2017.12.006⟩
Article dans une revue hal-01860402 v1
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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-04060973 v1
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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. Roure et al.
Journal of Nuclear Materials, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩
Article dans une revue cea-02389290 v1
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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 Jolu et al.
EPJ N - Nuclear Sciences & Technologies, 2016, 2, pp.22. ⟨10.1051/epjn/2016016⟩
Article dans une revue cea-01350715 v1
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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-01199597 v1

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 Sercombe et al.
Computers & Mathematics with Applications, 2015, 70 (5), pp.994-1023. ⟨10.1016/j.camwa.2015.06.027⟩
Article dans une revue cea-03306589 v1
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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-04825110 v1
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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-01057281 v1
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Experimental characterization and modelling of UO2 behavior at high temperatures and high strain rates

Maxime Salvo , Sercombe Jérôme , Jean-Claude Ménard , Jérôme Julien , Thomas Helfer et al.
Journal of Nuclear Materials, 2014, Volume 456, pp 54-67. ⟨10.1016/j.jnucmat.2014.09.024⟩
Article dans une revue hal-01199576 v1
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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-04652852 v1
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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-03427490 v1
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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-04652972 v1

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-02093543 v1
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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-02514885 v1

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-02887343 v1

Modelling of bituminized radioactive waste leaching. Part II: Experimental validation

B. Gwinner , J. Sercombe , C. Tiffreau , B. Simondi-Teisseire , I. Felines et 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-03018229 v1

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. Adenot et al.
Cement and Concrete Research, 2006, 36, pp.137-143
Article dans une revue hal-00119809 v1
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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-02360113 v1

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-03018230 v1
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Stockage en profondeur des déchets nucléaires bitumés

B. Gwinner , J. Sercombe , B. Simondi-Teisseire , I. Felines , C. Tiffreau et al.
Environnement, Ingénierie & Développement, 2004, N°36 - 4ème Trimestre 2004, pp.13-18. ⟨10.4267/dechets-sciences-techniques.2141⟩
Article dans une revue hal-03176881 v1

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 Colin et al.
8th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2023, Luca, Italy
Communication dans un congrès hal-04456882 v1
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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-04652480 v1

Laser-based experiments to investigate nuclear fuels behaviour under thermal stresses

Thomas Doualle , Matthieu Reymond , Vincent Klosek , Jérôme Sercombe , Laurent Gallais et al.
E-MRS 2022, 2022, En ligne, France
Communication dans un congrès hal-03917303 v1

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-03672602 v1

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-03466324 v1
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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-02614121 v1

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-02613566 v1

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-02613616 v1
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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-02339455 v1
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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-02400191 v1
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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. Fregonese et al.
TOPFUEL 2018 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Prague, Czech Republic
Communication dans un congrès cea-02400207 v1
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SIMULATION OF RIA TRANSIENTS ON MOX FUEL RODS WITH ALCYONE FUEL PERFORMANCE CODE

I Guénot-Delahaie , J. Sercombe , A Bouloré , É Fédérici , R Largenton et al.
TopFuel 2018 Reactor Fuel Performance Meeting, Sep 2018, Prague, Czech Republic
Communication dans un congrès hal-01889141 v1
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Simulation of RIA transients on MOX fuel rods with ALCYONE fuel performance code

I. Guenot-Delahaie , Jérôme Sercombe , Antoine Bouloré , Eric Federici , Rodrigue Largenton et al.
TopFuel2018 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Prague, Czech Republic
Communication dans un congrès cea-02338540 v1
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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 Fédérici et al.
WRFPM 2017, Sep 2017, JEJU Island, South Korea
Communication dans un congrès hal-01860413 v1

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 Jolu et al.
WRFPM 2017 (TOPFUEL), Sep 2017, Jeju-do, South Korea
Communication dans un congrès hal-02417383 v1
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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. Federici et al.
WRFPM 2017 Water Reactor Fuel Performance Meeting, Sep 2017, Jeju Island, South Korea
Communication dans un congrès hal-02433897 v1
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3d thermo-chemical-mechanical simulation of power ramps with alcyone fuel code

B. Baurens , J. Sercombe , C. Riglet-Martial , L. Desgranges , L. Trotignon et al.
Top Fuel 2015, Sep 2015, Zurich, Switzerland
Communication dans un congrès cea-02509262 v1

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. Salvo et al.
MMSNF-Nufuel, Nov 2015, Karlsruhe, Germany
Communication dans un congrès hal-02416330 v1
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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 Jolu et al.
Top Fuel 2015, Sep 2015, Zurich, Switzerland
Communication dans un congrès cea-02500835 v1
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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-02874737 v1
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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-03441360 v1
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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-03441407 v1

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-03306703 v1
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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-00589998 v1

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-04447310 v1
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Two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL

Bruno Michel , Isabelle Ramière , Isabelle Viallard , Clément Introini , Marc Lainet et 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-03581238 v1
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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-04825099 v1