Jérôme Sercombe

Ingénieur chercheur IRESNE
72 %
Libre accès
64
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

14
7
5
4
4
4
4
3
2
2
2
2
2
1
1
1
1
1
1
1
1
1
6
5
5
4
4
3
3
3
3
3
3
3
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
12
7
7
7
7
7
5
5
5
4
4
4
4
4
4
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
15
5
4
2
1
1
1
1
1
1
1
1
1
1
1
6
7
6
3
4
6
4
2
6
4
4
1
1
1
2
1
4
1
21
16
4
2
5
1
8
2
1
1

Publications

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 Pontillon et 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 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-04456882v1
Deposit thumbnail

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 Gallais et 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
Deposit thumbnail

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-02613566v1

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
Deposit thumbnail

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
Deposit thumbnail

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
Deposit thumbnail

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-02400207v1
Deposit thumbnail

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-02338540v1
Deposit thumbnail

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-01889141v1
Deposit thumbnail

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-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 Jolu et al.

WRFPM 2017 (TOPFUEL), Sep 2017, Jeju-do, South Korea

Communication dans un congrès hal-02417383v1
Deposit thumbnail

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-02433897v1
Deposit thumbnail

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-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. Salvo et al.

MMSNF-Nufuel, Nov 2015, Karlsruhe, Germany

Communication dans un congrès hal-02416330v1
Deposit thumbnail

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-02500835v1
Deposit thumbnail

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

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
Deposit thumbnail

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
Deposit thumbnail

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
Deposit thumbnail

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
Deposit thumbnail

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-04276119v1
Deposit thumbnail

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-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. Introïni et al.

Nuclear Technology, 2023, 210 (2), pp.285-307. ⟨10.1080/00295450.2023.2253660⟩

Article dans une revue cea-04652862v1
Deposit thumbnail

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
Deposit thumbnail

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-04412911v1
Deposit thumbnail

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-04018896v1
Deposit thumbnail

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-04018893v1
Deposit thumbnail

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-03713987v1

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-04276169v1
Deposit thumbnail

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-04018889v1
Deposit thumbnail

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
Deposit thumbnail

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

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-04276172v1
Deposit thumbnail

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-02426429v1

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
Deposit thumbnail

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-02405439v1
Deposit thumbnail

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-01860402v1
Deposit thumbnail

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
Deposit thumbnail

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-02389290v1
Deposit thumbnail

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-01350715v1
Deposit thumbnail

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

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-03306589v1
Deposit thumbnail

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
Deposit thumbnail

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
Deposit thumbnail

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
Deposit thumbnail

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-01199576v1
Deposit thumbnail

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
Deposit thumbnail

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
Deposit thumbnail

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

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

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. Adenot et 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. 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-03018229v1
Deposit thumbnail

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
Deposit thumbnail

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-03176881v1
Deposit thumbnail

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-03581238v1
Deposit thumbnail

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