Yves Pontillon

Publications

Article dans une revue (29)

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
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
A laser-based system to heat nuclear fuel pellets at high temperature C. Cifuentes Quintal,M. Reymond,F. Fiorito,F. Martin,M. Pontillonet al. Review of Scientific Instruments, 2023, 94 (10), ⟨10.1063/5.0139508⟩ Article dans une revue hal-04453724v1
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
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
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
Optical system for real-time monitoring of nuclear fuel pellets at high temperature Thibault Vidal,Laurent Gallais,Romain Burla,Frederic Martin,Hélène Capdevilaet al. Nuclear Engineering and Design, 2020, 357, pp.110383. ⟨10.1016/j.nucengdes.2019.110383⟩ Article dans une revue hal-02426983v1
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
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
A high power laser facility to conduct annealing tests at high temperature M. Minissale,A. Durif,P. Hiret,Thierry Vidal,J. Faucheuxet al. Review of Scientific Instruments, 2020, 91 (3), pp.035102. ⟨10.1063/1.5133741⟩ Article dans une revue hal-03164162v1
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
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. Volleet al. Review of Scientific Instruments, 2018, 89 (1), pp.013110. ⟨10.1063/1.4996611⟩ Article dans une revue hal-02426121v1
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. Desgrangeset al. Journal of Nuclear Materials, 2018, 507, pp.145-150. ⟨10.1016/j.jnucmat.2018.04.046⟩ Article dans une revue cea-02429995v1
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-Duringet al. Journal of Nuclear Materials, 2017, 495, pp.363-384. ⟨10.1016/j.jnucmat.2017.08.021⟩ Article dans une revue cea-02388710v1
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 Pontillonet 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
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. Bonninet al. Annals of Nuclear Energy, 2017, 101, pp.109-117. ⟨10.1016/j.anucene.2016.09.045⟩ Article dans une revue cea-02380827v1
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. Lamontagneet al. Journal of Nuclear Materials, 2017, 495, pp.49-57. ⟨10.1016/j.jnucmat.2017.08.002⟩ Article dans une revue cea-02388727v1
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. Lamontagneet al. Journal of Nuclear Materials, 2017, 495, pp.291-298. ⟨10.1016/j.jnucmat.2017.08.001⟩ Article dans une revue cea-02380864v1
Insights on Fission Products behaviour in Nuclear Severe Accident Conditions by X-ray Absorption Spectroscopy E. Geiger,R. Bes,Ph Martin,Yves Pontillon,G. Ducroset 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. Bernardet al. Nuclear Engineering and Design, 2014, 277, pp.117-123. ⟨10.1016/j.nucengdes.2014.05.045⟩ Article dans une revue hal-02641712v1
Annealing tests of in-pile irradiated oxide coated U-Mo/Al-Si dispersed nuclear fuel T. Zweifel,Ch. Valot,Yves Pontillon,J. Lamontagne,A. Vermerschet 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
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
Analysis of Fission Gas Release Kinetics by On-Line Mass Spectrometry Yves Zerega,Christelle Reynard-Carette,Daniel Parrat,Michel Carette,Boris Brkicet al. IEEE Transactions on Nuclear Science, 2012, 59 (4), pp.1323-1334. ⟨10.1109/TNS.2011.2179315⟩ Article dans une revue cea-02073557v1
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. Lamontagneet 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. Davidovichet 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. Ducroset 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. Carboneraet 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

Communication dans un congrès (56)

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. Richaudet al. ANIMMA25, 2025, Valence, Spain Communication dans un congrès hal-05519730v1
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
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 Thévenotet 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 Richouet al. Journées de la Matière Condensée, 2024, Marseille, France Communication dans un congrès hal-04909411v1
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. Massoneet 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 Broset 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 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
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
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 Lenciet al. 13th International Workshop on Subsecond Thermophysics IWSSTP-13, 2022, karlsruhe, Germany Communication dans un congrès hal-03751049v1
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
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
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 Richouet al. 11ème Forum Lasers et Plasmas, 2021, Belgodere, France Communication dans un congrès hal-03466348v1
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 Baldinozziet 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 Lenciet al. The Nineteenth International Conference on Fusion Reactor Materials, 2019, La Jolla, United States Communication dans un congrès hal-02426816v1
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
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. Solariet al. The 2018 MRS Spring Meeting & Exhibit, Apr 2018, Phoenix, United States Communication dans un congrès cea-02338951v1
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
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-Aubrunet al. NUMAT 2018 - The Nuclear Materials Conference 2018, Oct 2018, Seattle, United States Communication dans un congrès cea-02338475v1
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
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
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
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
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. Blayet al. HOTLAB, Sep 2018, Helsinki, Finland Communication dans un congrès cea-02328971v1
Development of experimental platform for analysis and imaging of fuel pellets heated at high temperature Thibault Vidal,R. Burla,L. Gallais,F. Martin,H. Capdevilaet al. Topfuel 2018 - 2018 Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Pragues, Czech Republic Communication dans un congrès cea-02338472v1
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 Pontillonet al. OECD/NEA Workshop Enhancing experimental support for advancements in Nuclear fuels and materials, Jan 2018, Paris, France Communication dans un congrès hal-02415308v1
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. Basiniet al. HOT LAB 2017, Sep 2017, Mito, Japan Communication dans un congrès hal-02418108v1
CoreSOAR Core Degradation SOAR Update Status May 2017 T. Haste,M. Barrachin,F. Fichot,G. Repetto,A. Miassoedovet al. 8th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland Communication dans un congrès hal-02418127v1
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. Ducroset 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
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. Léchelleet 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
MEXIICO a new equipment to study the pressure impact on the irradiated fuel behavior E. Hanus,P. Malgouyres,S. Clement,R. Alloncle,M. Pontillonet al. Top Fuel Meeting 2016, Sep 2016, Boise, United States Communication dans un congrès cea-02438357v1
Fission products behaviour in UO2 submitted to nuclear severe accident conditions E. Geiger,R. Bes,P. Martin,Yves Pontillon,P. L. Solariet 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
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
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. Bernardet al. Top Fuel, Sep 2016, Boise, United States Communication dans un congrès cea-02438702v1
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
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 Pontillonet al. HRP / WGFS LOCA Workshop, May 2015, Aix-en-Provence, France Communication dans un congrès cea-01599153v1
Main outcomes relative to iodine behaviour from the VERDON/ISTP programme Yves Pontillon,S. Bernard,A. Gallais-During,B. Gleizes,E. Hanuset 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
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. Hanuset 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
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
About nuclear fuels on MARS P. Martin,R. Bes,E. Geiger,V. Pennisi,P. Matheronet al. SUM2015 - Soleil User Meeting 2015, Jan 2015, Palaiseau, France Communication dans un congrès cea-02506792v1
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 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
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
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
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

Poster de conférence (7)

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. Faucheuxet 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 Capdevilaet 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 Baldinozziet al. Matériaux 2018. Colloque 14 – Matériaux en environnements extrêmes, Nov 2018, Strasbourg, France Poster de conférence hal-01933127v1
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. Ducroset 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