Yves Pontillon

92
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Publications

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Assessment of thermal effects in laser micro-machining of graphite with ultrashort pulses at high repetition rate

C.E. Cifuentes Quintal , T. Doualle , Y. Pontillon , J L Rullier , L. Gallais

Applied physics. A, Materials science & processing, 2025, 131 (7), pp.536. ⟨10.1007/s00339-025-08642-4⟩

Article dans une revue hal-05519683v1
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A Simple Modeling for Gas Release During Annealing of Irradiated Nuclear Fuel

Jimmy Losfeld , Lionel Desgranges , Yves Pontillon , Gianguido Baldinozzi

Transactions of the American Nuclear Society, 2023, 128 (1), pp.404-407

Article dans une revue hal-04459527v1
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A laser-based system to heat nuclear fuel pellets at high temperature

C. Cifuentes Quintal , M. Reymond , F. Fiorito , F. Martin , M. Pontillon et al.

Review of Scientific Instruments, 2023, 94 (10), ⟨10.1063/5.0139508⟩

Article dans une revue hal-04453724v1
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High power continuous wave laser heating of graphite in a high temperature range up to 3800 K

L. Gallais , T. Vidal , E. Lescoute , Y. Pontillon , J. Rullier

Journal of Applied Physics, 2021, 129 (4), pp.043102. ⟨10.1063/5.0033530⟩

Article dans une revue hal-03466241v1
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Laser ablation of graphite with near infrared microsecond pulses

T. Doualle , M. Reymond , Y. Pontillon , L. Gallais

Applied physics. A, Materials science & processing, 2021, 127 (9), pp.722. ⟨10.1007/s00339-021-04815-z⟩

Article dans une revue hal-03466235v1
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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-03466237v1
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Optical system for real-time monitoring of nuclear fuel pellets at high temperature

Thibault Vidal , Laurent Gallais , Romain Burla , Frederic Martin , Hélène Capdevila et al.

Nuclear Engineering and Design, 2020, 357, pp.110383. ⟨10.1016/j.nucengdes.2019.110383⟩

Article dans une revue hal-02426983v1
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Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO 2 on Cs, Mo and Ba speciation

Claire Le Gall , F. Audubert , Jacques Léchelle , Yves Pontillon , Jean-Louis F Hazemann

EPJ N - Nuclear Sciences & Technologies, 2020, 6, pp.2. ⟨10.1051/epjn/2019058⟩

Article dans une revue cea-02458380v1
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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-02426429v1
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A high power laser facility to conduct annealing tests at high temperature

M. Minissale , A. Durif , P. Hiret , Thierry Vidal , J. Faucheux et al.

Review of Scientific Instruments, 2020, 91 (3), pp.035102. ⟨10.1063/1.5133741⟩

Article dans une revue hal-03164162v1
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Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident

E. Geiger , C. Guéneau , Y. Pontillon , E.C. Corcoran

Journal of Nuclear Materials, 2019, 522, pp.294 - 310. ⟨10.1016/j.jnucmat.2019.05.027⟩

Article dans une revue hal-03487013v1
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New insight in the uranium valence state determination in U$_y$Nd$_{1−y}$O$_{2 \pm x}$

R. Bès , K. Kvashnina , A. Rossberg , G. Dottavio , L. Desgranges et al.

Journal of Nuclear Materials, 2018, 507, pp.145-150. ⟨10.1016/j.jnucmat.2018.04.046⟩

Article dans une revue cea-02429995v1

An experimental platform for real-time measurement of the deformation of nuclear fuel rod claddings submitted to thermal transients

L. Gallais , R. Burla , F. Martin , J. Richaud , G. Volle et al.

Review of Scientific Instruments, 2018, 89 (1), pp.013110. ⟨10.1063/1.4996611⟩

Article dans une revue hal-02426121v1
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Fission products and nuclear fuel behavior under severe accident conditions Part 3: Fission Products speciation in the VERDON-1 Sample

C. Le Gall , E. Geiger , A. Gallais-During , Yves Pontillon , J. Lamontagne et al.

Journal of Nuclear Materials, 2017, 495, pp.291-298. ⟨10.1016/j.jnucmat.2017.08.001⟩

Article dans une revue cea-02380864v1
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Fission products and nuclear fuel behavior under severe accident conditions Part 2: Fuel behavior in the VERDON-1 sample

E. Geiger , Le Gall Claire , A. Gallais-During , Yves Pontillon , J. Lamontagne et al.

Journal of Nuclear Materials, 2017, 495, pp.49-57. ⟨10.1016/j.jnucmat.2017.08.002⟩

Article dans une revue cea-02388727v1
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When combined X-ray and polarized neutron diffraction data challenge high-level calculations: spin-resolved electron density of an organic radical

Ariste Bolivard Voufack , Nicolas Claiser , Claude Lecomte , Sébastien Pillet , Yves Pontillon et al.

Acta Crystallographica Section B : Structural Science, Crystal Engineering and Materials [2014-..], 2017, 73 (4), pp.544-549. ⟨10.1107/S2052520617008241⟩

Article dans une revue hal-02196484v1
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Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test

Yves Pontillon , E. Geiger , C. Le Gall , S. Bernard , A. Gallais-During et al.

Journal of Nuclear Materials, 2017, 495, pp.363-384. ⟨10.1016/j.jnucmat.2017.08.021⟩

Article dans une revue cea-02388710v1

Overview of the VERDON-ISTP Program and main insights from the VERDON-2 air ingress test

A. Gallais-During , S. Bernard , B. Gleizes , Yves Pontillon , J. Bonnin et al.

Annals of Nuclear Energy, 2017, 101, pp.109-117. ⟨10.1016/j.anucene.2016.09.045⟩

Article dans une revue cea-02380827v1
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Insights on Fission Products behaviour in Nuclear Severe Accident Conditions by X-ray Absorption Spectroscopy

E. Geiger , R. Bes , Ph Martin , Yves Pontillon , G. Ducros et al.

Journal of Nuclear Materials, 2016, 471, pp.25-33. ⟨10.1016/j.jnucmat.2015.12.032⟩

Article dans une revue cea-02383228v1

Performance and first results of fission product release and transport provided by the VERDON facility

A. Gallais-During , J. Bonnin , P.-P. Malgouyres , S. Morin , S. Bernard et al.

Nuclear Engineering and Design, 2014, 277, pp.117-123. ⟨10.1016/j.nucengdes.2014.05.045⟩

Article dans une revue hal-02641712v1
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Annealing tests of in-pile irradiated oxide coated U-Mo/Al-Si dispersed nuclear fuel

T. Zweifel , Ch. Valot , Yves Pontillon , J. Lamontagne , A. Vermersch et al.

Journal of Nuclear Materials, 2014, 452 (1-3), pp.533-547. ⟨10.1016/j.jnucmat.2014.05.052⟩

Article dans une revue hal-01021884v1

On-line deformation measurements of nuclear fuel rod cladding using speckle interferometry

Fabert Marc , Laurent Gallais , Yves Pontillon

Progress in Nuclear Energy, 2014, 72, pp.44. ⟨10.1016/j.pnucene.2013.10.009⟩

Article dans une revue istex hal-01097098v1

Analysis of Fission Gas Release Kinetics by On-Line Mass Spectrometry

Yves Zerega , Christelle Reynard-Carette , Daniel Parrat , Michel Carette , Boris Brkic et al.

IEEE Transactions on Nuclear Science, 2012, 59 (4), pp.1323-1334. ⟨10.1109/TNS.2011.2179315⟩

Article dans une revue cea-02073557v1

Feasibility Studies for Speckle Interferometry Used to Measure Deformation in Nuclear Fuel Cladding

Alexandre Vauselle , Yves Pontillon , Laurent Gallais

Nuclear Technology, 2012, 177, pp.285-292

Article dans une revue hal-00675482v1

Evidence of a biphasic domain in the UO 2-Nd 2O 3 diagram at low temperature: a proof for a miscibility gap in the UO 2-Nd 2O 3 phase diagram?

Lionel Desgranges , Mathieu Marcet , Yves Pontillon , Florence Porcher , J. Lamontagne et al.

Solid State Data - Pt B: Solid State Phenomena, 2011, 172-174, pp.624-629. ⟨10.4028/www.scientific.net/SSP.172-174.624⟩

Article dans une revue hal-00726077v1

Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident

P. Giordano , A. Auvinen , G. Brillant , J. Colombani , N. Davidovich et al.

Progress in Nuclear Energy, 2010, 52 (1), pp.109-119. ⟨10.1016/j.pnucene.2009.09.011⟩

Article dans une revue istex hal-02972643v1

Progress on ruthenium release and transport under air ingress conditions

A. Auvinen , G. Brillant , N. Davidovich , R. Dickson , G. Ducros et al.

Nuclear Engineering and Design, 2008, 238 (12), pp.3418-3428. ⟨10.1016/j.nucengdes.2008.07.010⟩

Article dans une revue istex hal-03005077v1

Combined Charge and Spin Density Experimental Study of the Yttrium(III) Semiquinonato Complex Y(HBPz3)2(DTBSQ) and DFT Calculations

N. Claiser , M. Souhassou , C. Lecomte , B. Gillon , C. Carbonera et al.

The Journal of physical chemistry, 2005, B109(7), pp.2723-2732. ⟨10.1021/jp0467907⟩

Article dans une revue istex hal-00021272v1

Images of unpaired electron density in molecular crystals obtained using experimentally constrained wavefunctions

D. Jayatilaka , A. Whitton , S. Pillet , Yves Pontillon , C. Lecomte

Acta Crystallographica Section A : Foundations of Crystallography [1968-2013], 2005, 61, pp.C48

Article dans une revue hal-00021284v1

Correlated release between Caesium and fission gases during LOCA type scenario

Florian Castermans , Lionel Desgranges , Rodrigue Largenton , Gianguido Baldinozzi , Yves Pontillon

NuMAT 2026, Sep 2026, Halifax (Canada), Canada

Communication dans un congrès hal-05524834v1

The MERARG Facility Performance: Correlation Between the Release of Fission Products and the Fragmentation of Irradiated Nuclear Fuel Subjected to Temperature Transients

O. Leroy , T. Doualle , F. Casterman , F. Fiorito , J.C. Richaud et al.

ANIMMA25, 2025, Valence, Spain

Communication dans un congrès hal-05519730v1

Development of Laser-Based Experimental Platforms for the Study of Thermophysical properties of Nuclear Irradiated Fuels at High Temperature

Yves Pontillon , Thomas Doualle , C. Cifuentes Quintal , Christian Colin , Caroline Thévenot et al.

22d Symposium on Thermophysical Properties (Thermosymposium), 2024, Boulder (CO), United States

Communication dans un congrès hal-04911082v1

Investigation of Laser Processing as a promising approach for the preparation of nuclear fuel ceramic samples in harsh environment

C. Cifuentes Quintal , Thomas Doualle , Yves Pontillon , Laurent Gallais

Procédés Laser pour l'Industrie (PLI2024), 2024, Bordeaux, France

Communication dans un congrès hal-04909429v1

Contribution of laser techniques for the study of fission and fusion materials at high temperature

Laurent Gallais , Marco Minissale , Thomas Doualle , Guillaume Kermouche , Marianne Richou et al.

Journées de la Matière Condensée, 2024, Marseille, France

Communication dans un congrès hal-04909411v1

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
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Synthesis of Source Term Assessments for a Loss-of-Cooling Accident in a Spent Fuel Pool: Insights from Uncertainty and Sensitivity analyses and potential benefit of water injection by spray system

Olivia Coindreau , Monica Garcia , Luis Enrique Herranz , S. Ederli , M. Massone et al.

The 11 th European Review Meeting on Severe Accident Research (ERMSAR2024), Kungliga Tekniska Högskolan, May 2024, Stochkolm, Sweden

Communication dans un congrès hal-04847726v1

New Experimental Devices for Severe Accident Study: a Laser Based Approach

Yves Pontillon , T. Doualle , Caroline Thévenot , C. Nonon , Pascal Bros et al.

European Review Meeting on Severe Accident Research (ERMSAR 2024), 2024, Stochholm, Sweden

Communication dans un congrès hal-04909269v1

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

Investigation of nuclear fuels behaviour under thermal stresses: new insights gained thanks to laser-based experiments

Yves Pontillon , Thomas Doualle , Matthieu Reymond , Vincent Klosek , Laurent Gallais

TopFuel 2022 Light Water Reactor Fuel Performance Conference, 2022, Raleigh, United States

Communication dans un congrès hal-03917342v1

Chauffage par laser pour l’étude des combustibles nucléaires portés à hautes-température

Carlos Cifuentes , Matthieu Reymond , Thomas Doualle , Yves Pontillon , Laurent Gallais

Matériaux 2022, 2022, Lille, France

Communication dans un congrès hal-03917313v1

Laser-based experiments to study the recrystallization kinetics of tungsten at high temperature’

M. Lemetais , Marco Minissale , Alan Durif , Marianne Richou , Matthieu Lenci et al.

13th International Workshop on Subsecond Thermophysics IWSSTP-13, 2022, karlsruhe, Germany

Communication dans un congrès hal-03751049v1

Investigation of nuclear fuels behaviour under thermal stresses: New insights gained thanks to Laser-based experiments

Thomas Doualle , Yves Pontillon , Matthieu Reymond , Vincent Klosek , Laurent Gallais

13th International Workshop on Subsecond Thermophysics IWSSTP-13, 2022, Karlsruhe, Germany

Communication dans un congrès hal-03751053v1

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

High power CW laser heating of graphite at high temperature and applications in material studies and laser processing’

Laurent Gallais , Thomas Doualle , Yves Pontillon , Jean-Luc Rullier

Advanced Laser Technologies – ALT21, 2021, Moscou (on line), Russia

Communication dans un congrès hal-03466320v1

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

Laser micro-processing of graphite with pulsed ytterbium laser

Thomas Doualle , Matthieu Reymond , Yves Pontillon , Laurent Gallais

Advanced Laser Technologies – ALT21, 2021, on line, Russia

Communication dans un congrès hal-03466344v1

High power CW laser heating for the study of materials at very high temperature

Laurent Gallais , Guillaume Kermouche , Marco Minissale , Yves Pontillon , Marianne Richou et al.

11ème Forum Lasers et Plasmas, 2021, Belgodere, France

Communication dans un congrès hal-03466348v1
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Using laser remote heating to simulate extreme thermal heat loads on nuclear fuels

Thibault Vidal , Laurent Gallais , J. Faucheux , H. Capdevila , Yves Pontillon

International conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 2019, Portoroz, Slovenia. pp.08002, ⟨10.1051/epjconf/202022508002⟩

Communication dans un congrès hal-02426436v1

Influence of the miscibility gap in the evolution of the microstructure in UO2-based fuel doped with Nd

Bernardo Alex Herrero-Bocco , F. Audubert , Yves Pontillon , Lionel Desgranges , Gianguido Baldinozzi et al.

2019 TMS Annual Meeting & Exhibition. Symposium: Ceramic Materials for Nuclear Energy Research and Applications, Mar 2019, San Antonio, United States

Communication dans un congrès hal-01930225v1

A high power laser facility to submit plasma facing materials to extreme heats loads

M. Minissale , A. Durif , Vidal Thibault , J. Faucheux , Matthieu Lenci et al.

The Nineteenth International Conference on Fusion Reactor Materials, 2019, La Jolla, United States

Communication dans un congrès hal-02426816v1
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New Insight on Volatile Fission Products (I and Cs) release from high burnup UO$_2$ fuel under LOCA type conditions

Yves Pontillon , I. Moysan , S. Bernard , M. Ledieu

TOPFUEL 2018 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Prague, Czech Republic

Communication dans un congrès cea-02338477v1
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Development of experimental platform for analysis and imaging of fuel pellets heated at high temperature

Thibault Vidal , R. Burla , L. Gallais , F. Martin , H. Capdevila et al.

Topfuel 2018 - 2018 Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Pragues, Czech Republic

Communication dans un congrès cea-02338472v1
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Shielded Electron Microprobe and some of its main applications in HotlabsCharacterization of MOX irradiated fuels treated at very high temperatures

A. Moret , C. Le Gall , K. Hanifi , I. Felines , T. Blay et al.

HOTLAB, Sep 2018, Helsinki, Finland

Communication dans un congrès cea-02328971v1

Some pending issues in nuclear fuel and in-core materials development for LWRs experimental support for modeling and simulation

J.-C. Brachet , C. Valot , Daniel Parrat , E. Federici , Yves Pontillon et al.

OECD/NEA Workshop Enhancing experimental support for advancements in Nuclear fuels and materials, Jan 2018, Paris, France

Communication dans un congrès hal-02415308v1
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Fission products and nuclear fuel behaviour under severe accident conditionsSpeciation of fission productsin the Verdon 3 and -4 samples

F. Audubert , C. Le Gall , L. Fayette , P. Bienvenu , I. Zacharie-Aubrun et al.

NUMAT 2018 - The Nuclear Materials Conference 2018, Oct 2018, Seattle, United States

Communication dans un congrès cea-02338475v1

Développement d’une plateforme expérimentale pour simuler la thermique d’un accident de réactivité (RIA) à l’échelle du laboratoire sur le combustible nucléaire

Vidal Thibault , Laurent Gallais , J. Faucheux , H. Capdevila , Yves Pontillon

Rencontre scientifique MINOS – VII ((Materials Innovation for Nuclear Optimized Systems), 2018, cadarache, France

Communication dans un congrès hal-02426369v1
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Using laser remote heating to simulate extreme thermal loads on nuclear fuels

Thierry Vidal , L. Gallais , J. Faucheux , H. Capdevila , Yves Pontillon

Topfuel 2018, Sep 2018, Prague, Czech Republic

Communication dans un congrès cea-02338471v1
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Oxide phase characterization in simulated high burn-up UO$_2$ fuels in the early stages of a nuclear severe accident

C. Le Gall , E. Geiger , O. Proux , M. Rovezzi , P.L. Solari et al.

The 2018 MRS Spring Meeting & Exhibit, Apr 2018, Phoenix, United States

Communication dans un congrès cea-02338951v1

An auto-catalytic mechanism to model the fission gas release between 600°C and 800°C on UO2 irradiated fuel

Yves Pontillon , Guillaume Brindelle , Gianguido Baldinozzi , Hélène Capdevila , Lionel Desgranges

MRS Spring Meeting 2018. Fundamental Materials Science to Enable the Performance and Safety of Nuclear Technologies. Symp EN17, Apr 2018, Phoenix, United States

Communication dans un congrès hal-01929939v1
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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-02400191v1
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An auto-catalytic mechanism to model the fission gas release between 600°C and 800°C on UO$_2$ irradiated fuel.

Yves Pontillon , G. Brindelle , G. Baldinozzi , H. Capdevila , L. Desgranges

MRS spring 2018, Apr 2018, Phoenix, United States

Communication dans un congrès cea-02339066v1

Chauffage contrôlé par Laser pour la simulation de charges thermiques sur des matériaux et assemblages pour le nucléaire’

Vidal Thibault , Laurent Gallais , J. Faucheux , Hélène Capdevila , Yves Pontillon

Conférence MATERIAUX, 2018, strasbourg, France

Communication dans un congrès hal-02426352v1
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CoreSOAR Core Degradation SOAR Update Status May 2017

T. Haste , M. Barrachin , F. Fichot , G. Repetto , A. Miassoedov et al.

8th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland

Communication dans un congrès hal-02418127v1
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Design and implementation of a new gamma spectrometry sighting device for gaseous iodine measurements in the VERDON CET-loop

M. Ledieu , S. Bernard , B. Gleizes , Yves Pontillon , G. Ducros et al.

International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA - 2017), Jun 2017, Liege, Belgium

Communication dans un congrès hal-02417817v1

Severe Accident Research activities at the CEA Methodology and Main Insights Related to Source Term Quantification and Fuel Behavior.

Yves Pontillon , F. Audubert , C. Legall , E. Geiger , V. Basini et al.

HOT LAB 2017, Sep 2017, Mito, Japan

Communication dans un congrès hal-02418108v1
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An innovative Method to study Volatile Fission Products speciation in nuclear fuels under Severe Accident Conditions

H. Hein , Jl. Hazemann , O. Proux , C. Riglet-Martial , J. Léchelle et al.

8th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland

Communication dans un congrès cea-02434559v1

Développement d’un interférométre de speckle à 2 longueurs d’ondes pour la mesures de déformation de crayons de combustible nucléaire en chauffe

Laurent Gallais , Romain Burla , Yves Pontillon

CMOI : Conférence Mesures Optiques pour l'Industrie, 2017, Le Mans, France

Communication dans un congrès hal-01588241v1
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An auto-catalytic mechanism to explain the fission gas release between 500°c and 800°c on UO$_2$ irradiated fuel

G. Brindelle , Yves Pontillon , H. Capdevila , L. Desgranges , G. Baldinozzi

Numat2016, Nov 2016, Montpellier, France

Communication dans un congrès cea-02437063v1
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Fission products behaviour in UO2 submitted to nuclear severe accident conditions

E. Geiger , R. Bes , P. Martin , Yves Pontillon , P. L. Solari et al.

16th International Conference on X-ray Absorption Fine Structure (XAFS), Aug 2015, Karlsruhe, Germany. 4 p., ⟨10.1088/1742-6596/712/1/012098⟩

Communication dans un congrès hal-01572977v1
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Increasing of MERARG Experimental Performances On-line Fission Gas Release Measurement by Mass Spectrometry

Elodie Guigues , Aurika Janulyte , Yves Zerega , Yves Pontillon , Jacques Andre

ANIMMA 2015 - 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, Apr 2015, Lisbonne, Portugal. pp.1703-1709, ⟨10.1109/TNS.2016.2554610⟩

Communication dans un congrès cea-02509250v1

Thin film samples: a new methodology for investigating the mechanisms of fission gas releases from nuclear fuel during a LOCA

Guillaume Brindelle , Gianguido Baldinozzi , Hélène Capdevila , Lionel Desgranges , Yves Pontillon

2016 MRS Spring Meeting, Materials Research Society, Mar 2016, Phoenix, United States. pp.2439 - 2445, ⟨10.1557/adv.2016.501⟩

Communication dans un congrès hal-01481517v1
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MEXIICO a new equipment to study the pressure impact on the irradiated fuel behavior

E. Hanus , P. Malgouyres , S. Clement , R. Alloncle , M. Pontillon et al.

Top Fuel Meeting 2016, Sep 2016, Boise, United States

Communication dans un congrès cea-02438357v1
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Nuclear fuel behaviour at high temperature new insights from post-test examinations on the VERDON-1 sample

A. Gallais-During , E. Geiger , C. Le Gall , J. Lamontagne , S. Bernard et al.

Top Fuel, Sep 2016, Boise, United States

Communication dans un congrès cea-02438702v1
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About nuclear fuels on MARS

P. Martin , R. Bes , E. Geiger , V. Pennisi , P. Matheron et al.

SUM2015 - Soleil User Meeting 2015, Jan 2015, Palaiseau, France

Communication dans un congrès cea-02506792v1
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Implementation of a new gamma spectrometer on the MERARG loop Application to the volatile fission products release measurement.

B. Cornu , S. Bernard , Yves Pontillon , B. Gleizes , E. Hanus et al.

ANIMMA 2015 - International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications, Apr 2015, Lisbonne, Portugal

Communication dans un congrès cea-02509259v1

Charge distribution in doped uranium dioxide

Lionel Desgranges , Gianguido Baldinozzi , Giannina Dottavio , Yves Pontillon

45èmes Journées des Actinides, Charles University in Prague, Department of condensed Matter Physics, Apr 2015, Prague - Pruhonice, Czech Republic

Communication dans un congrès hal-01230637v1
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Size and radial origin of fragments formed while heating a 83 GWd/t$_U$ PWR fuel up to 1200 °C

J. Noirot , Th Blay , J. Lamontagne , L Fayette , Yves Pontillon et al.

HRP / WGFS LOCA Workshop, May 2015, Aix-en-Provence, France

Communication dans un congrès cea-01599153v1
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Use of model materials for fission products release study in Severe Accident Conditions

E. Geiger , R. Bes , Yves Pontillon , P. Martin , G. Ducros

ERMSAR 2015 - 7th European Review Meeting on Severe Accident Research, Mar 2015, Marseille, France

Communication dans un congrès cea-02509278v1
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Main outcomes relative to iodine behaviour from the VERDON/ISTP programme

Yves Pontillon , S. Bernard , A. Gallais-During , B. Gleizes , E. Hanus et al.

International OECD/NEA-NUGENIA/SARNET Workshop on the Progress in Iodine Behaviour for NPP Accident Analysis and Management, Mar 2015, Marseille, France

Communication dans un congrès cea-02509274v1

On-line deformation measurements of nuclear fuel rod cladding using speckle interferometry

Fabert Marc , Laurent Gallais , Yves Pontillon

E-MRS 2013 Spring meeting, 2013, Strasbourg, France

Communication dans un congrès hal-00854940v1

Interférométrie de speckle pour la mesure de déformations du gainage de combustibles nucléaires

Fabert Marc , Laurent Gallais , Yves Pontillon

CMOI 2013, 2013, Paris, France. pp.X

Communication dans un congrès hal-00937947v1

Mesure de d éformations du gainage de combustible nucléaire par Interférométrie de Speckle

Fabert Marc , Laurent Gallais , Yves Pontillon

Optique Paris 2013 (Horizons de l'Optique), 2013, Paris, France

Communication dans un congrès hal-00854936v1

On-line cladding deformation measurements of nuclear fuel rods submitted to analytical transient conditions

Fabert Marc , Laurent Gallais , Yves Pontillon

European Nuclear Conference, Dec 2012, manchester, United Kingdom

Communication dans un congrès hal-00764765v1

In situ measurements of nuclear fuel rod cladding deformation by speckle interferometry

Fabert Marc , Laurent Gallais , Yves Pontillon

49th Conference on Hot Laboratories and Remote Handling, Sep 2012, Marcoule, France

Communication dans un congrès hal-00764776v1

Development of an optical method to measure deformations of nuclear fuel cladding

Alexandre Vauselle , Yves Pontillon , Laurent Gallais

Hot laboratories and remote handling, Sep 2009, Prague, Czech Republic

Communication dans un congrès hal-00420296v1
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Is there a chemical form of cesium involved in the release of fission gases?

Florian Castermans , Lionel Desgranges , Yves Pontillon , Rodrigue Largenton , Gianguido Baldinozzi

JEEP2025 : Journées d'Etude des Equilibres entre Phases, Mar 2025, Paris, France. 2025

Poster de conférence hal-05304321v1

Exploring laser ultra-fast ablation technique on UO2: advancements in Nuclear fuel micro-machining

C. Cifuentes Quintal , Thomas Doualle , Yves Pontillon , Laurent Gallais

Conference On Laser Ablation (COLA), 2024, Heraklion (Crete Island), Greece

Poster de conférence hal-04890077v1

A high power laser facility to submit plasma facing materials to extreme heat loads

M. Minissale , A. Durif , Vidal Thibault , Paul Hiret , J. Faucheux et al.

The 17th International Conference on Plasma-Facing Materials and Components for Fusion (PFMC19), 2019, Eindhoven, Netherlands

Poster de conférence hal-02426836v1

Development of experimental platform for analysis and imaging of fuel pellets heated at high temperature

Vidal Thibault , Laurent Gallais , Romain Burla , Frédéric Martin , Hélène Capdevila et al.

TopFuel 2018, 2018, prague, Czech Republic

Poster de conférence hal-02426361v1

Influence of the miscibility gap in the evolution of the microstructure in UO2-based fuel doped with Nd

Bernardo Herrero , F. Audubert , Lionel Desgranges , Yves Pontillon , Gianguido Baldinozzi et al.

Matériaux 2018. Colloque 14 – Matériaux en environnements extrêmes, Nov 2018, Strasbourg, France

Poster de conférence hal-01933127v1
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Implementation of a new gamma spectrometry device on the VERDON CET loop to measure iodine release kinetics

S. Bernard , M. Ledieu , B. Gleizes , Yves Pontillon , G. Ducros et al.

International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA - 2017 - LIEGE), Jun 2017, Liege, Belgium. International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA - 2017 - LIEGE), 2017

Poster de conférence hal-02417798v1

An auto-catalytic mechanism to model the fission gas release between 500°C and 800°C on UO2 irradiated fuel

Guillaume Brindelle , Gianguido Baldinozzi , Hélène Capdevila , Lionel Desgranges , Yves Pontillon

NuMat2016: The Nuclear Materials Conference, Nov 2016, Montpellier, France. , 2016

Poster de conférence hal-01480689v1