Yves Pontillon

Documents

Publications

	A laser-based system to heat nuclear fuel pellets at high temperature C. Cifuentes Quintal , M. Reymond , F. Fiorito , F. Martin , M. Pontillon Review of Scientific Instruments, 2023, 94 (10), ⟨10.1063/5.0139508⟩ Article dans une revue hal-04453724v1
	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
	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
	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
	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
	Optical system for real-time monitoring of nuclear fuel pellets at high temperature Thibault Vidal , Laurent Gallais , Romain Burla , Frederic Martin , Hélène Capdevila Nuclear Engineering and Design, 2020, 357, pp.110383. ⟨10.1016/j.nucengdes.2019.110383⟩ Article dans une revue hal-02426983v1
	A high power laser facility to conduct annealing tests at high temperature M. Minissale , A. Durif , P. Hiret , Thierry Vidal , J. Faucheux Review of Scientific Instruments, 2020, 91 (3), pp.035102. ⟨10.1063/1.5133741⟩ Article dans une revue hal-03164162v1
	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. Sercombe Journal of Nuclear Materials, 2020, 530 (13), pp.151944. ⟨10.1016/j.jnucmat.2019.151944⟩ Article dans une revue hal-02426429v1
	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. Volle 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. Desgranges Journal of Nuclear Materials, 2018, 507, pp.145-150. ⟨10.1016/j.jnucmat.2018.04.046⟩ Article dans une revue cea-02429995v1
	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 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. Bonnin 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 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 Journal of Nuclear Materials, 2017, 495, pp.363-384. ⟨10.1016/j.jnucmat.2017.08.021⟩ Article dans une revue cea-02388710v1
	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 Journal of Nuclear Materials, 2017, 495, pp.291-298. ⟨10.1016/j.jnucmat.2017.08.001⟩ Article dans une revue cea-02380864v1
	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 Journal of Nuclear Materials, 2017, 495, pp.49-57. ⟨10.1016/j.jnucmat.2017.08.002⟩ Article dans une revue cea-02388727v1
	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 Journal of Nuclear Materials, 2016, 471, pp.25-33. ⟨10.1016/j.jnucmat.2015.12.032⟩ Article dans une revue cea-02383228v1
	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 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 hal-01097098v1
	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 Nuclear Engineering and Design, 2014, 277, pp.117-123. ⟨10.1016/j.nucengdes.2014.05.045⟩ Article dans une revue hal-02641712v1
	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 Brkic 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. Lamontagne 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 Progress in Nuclear Energy, 2010, 52 (1), pp.109-119. ⟨10.1016/j.pnucene.2009.09.011⟩ Article dans une revue hal-02972643v1
	Progress on ruthenium release and transport under air ingress conditions A. Auvinen , G. Brillant , N. Davidovich , R. Dickson , G. Ducros Nuclear Engineering and Design, 2008, 238 (12), pp.3418-3428. ⟨10.1016/j.nucengdes.2008.07.010⟩ Article dans une revue hal-03005077v1
	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
	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 The Journal of physical chemistry, 2005, B109(7), pp.2723-2732. ⟨10.1021/jp0467907⟩ Article dans une revue hal-00021272v1

	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 8th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2023, Luca, Italy Communication dans un congrès hal-04456882v1
	Laser-based experiments to study the recrystallization kinetics of tungsten at high temperature’ M. Lemetais , Marco Minissale , Alan Durif , Marianne Richou , Matthieu Lenci 13th International Workshop on Subsecond Thermophysics IWSSTP-13, 2022, karlsruhe, Germany Communication dans un congrès hal-03751049v1
	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 investigate nuclear fuels behaviour under thermal stresses Thomas Doualle , Matthieu Reymond , Vincent Klosek , Jérôme Sercombe , Laurent Gallais 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 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
	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
	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
	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
	High power CW laser heating for the study of materials at very high temperature Laurent Gallais , Guillaume Kermouche , Marco Minissale , Yves Pontillon , Marianne Richou 11ème Forum Lasers et Plasmas, 2021, Belgodere, France Communication dans un congrès hal-03466348v1
	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
	A high power laser facility to submit plasma facing materials to extreme heats loads M. Minissale , A. Durif , Vidal Thibault , J. Faucheux , Matthieu Lenci The Nineteenth International Conference on Fusion Reactor Materials, 2019, La Jolla, United States Communication dans un congrès hal-02426816v1
	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 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
	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
	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 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 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
	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
	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
	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
	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
	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 The 2018 MRS Spring Meeting & Exhibit, Apr 2018, Phoenix, United States Communication dans un congrès cea-02338951v1
	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 OECD/NEA Workshop Enhancing experimental support for advancements in Nuclear fuels and materials, Jan 2018, Paris, France Communication dans un congrès hal-02415308v1
	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. Blay 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 Thierry Vidal , R. Burla , L. Gallais , F. Martin , H. Capdevila Topfuel 2018 - 2018 Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2018, Pragues, Czech Republic Communication dans un congrès cea-02338472v1
	CoreSOAR Core Degradation SOAR Update Status May 2017 T. Haste , M. Barrachin , F. Fichot , G. Repetto , A. Miassoedov 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. Ducros 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. Léchelle 8th European Review Meeting on Severe Accident Research (ERMSAR - 2017), May 2017, Varsovie, Poland Communication dans un congrès cea-02434559v1
	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 HOT LAB 2017, Sep 2017, Mito, Japan Communication dans un congrès hal-02418108v1
	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
	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 Top Fuel, Sep 2016, Boise, United States Communication dans un congrès cea-02438702v1
	MEXIICO a new equipment to study the pressure impact on the irradiated fuel behavior E. Hanus , P. Malgouyres , S. Clement , R. Alloncle , M. Pontillon Top Fuel Meeting 2016, Sep 2016, Boise, United States Communication dans un congrès cea-02438357v1
	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
	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
	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 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
	Main outcomes relative to iodine behaviour from the VERDON/ISTP programme Yves Pontillon , S. Bernard , A. Gallais-During , B. Gleizes , E. Hanus 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
	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
	Increasing of MERARG Experimental Performances On-line Fission Gas Release Measurement by Mass Spectrometry Yves Pontillon , H. Capdevila , S. Clement , E. Guigues , A. Janulyte ANIMMA 2015 - 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, Apr 2015, Lisbone, Portugal. ⟨10.1109/TNS.2016.2554610⟩ Communication dans un congrès cea-02509250v1
	Fission products behaviour in UO2 submitted to nuclear severe accident conditions E. Geiger , R. Bes , P. Martin , Yves Pontillon , P. L. Solari 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
	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 HRP / WGFS LOCA Workshop, May 2015, Aix-en-Provence, France Communication dans un congrès cea-01599153v1
	About nuclear fuels on MARS P. Martin , R. Bes , E. Geiger , V. Pennisi , P. Matheron 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

	A high power laser facility to submit plasma facing materials to extreme heat loads M. Minissale , A. Durif , Vidal Thibault , Paul Hiret , J. Faucheux 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 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 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. Ducros 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

Yves Pontillon

Publications

A laser-based system to heat nuclear fuel pellets at high temperature

A Simple Modeling for Gas Release During Annealing of Irradiated Nuclear Fuel

Thermo-mechanical simulations of laser heating experiments on UO$_2$

Laser ablation of graphite with near infrared microsecond pulses

High power continuous wave laser heating of graphite in a high temperature range up to 3800 K

Optical system for real-time monitoring of nuclear fuel pellets at high temperature

A high power laser facility to conduct annealing tests at high temperature

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

Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating

Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident

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

New insight in the uranium valence state determination in U$_y$Nd$_{1−y}$O$_{2 \pm x}$

When combined X-ray and polarized neutron diffraction data challenge high-level calculations: spin-resolved electron density of an organic radical

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

Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test

Fission products and nuclear fuel behavior under severe accident conditions Part 3: Fission Products speciation in the VERDON-1 Sample

Fission products and nuclear fuel behavior under severe accident conditions Part 2: Fuel behavior in the VERDON-1 sample

Insights on Fission Products behaviour in Nuclear Severe Accident Conditions by X-ray Absorption Spectroscopy

Annealing tests of in-pile irradiated oxide coated U-Mo/Al-Si dispersed nuclear fuel

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

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

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

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

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?

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

Progress on ruthenium release and transport under air ingress conditions

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

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

High power Laser-based for nuclear fuels behaviour and properties investigation under extreme conditions

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

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

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

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

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

Laser micro-processing of graphite with pulsed ytterbium laser

Modeling of fuel behaviour during RIA transients: new insights gained thanks to laser heating experiments

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

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

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

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

Using laser remote heating to simulate extreme thermal heat loads on nuclear fuels

Fission products and nuclear fuel behaviour under severe accident conditionsSpeciation of fission productsin the Verdon 3 and -4 samples

An auto-catalytic mechanism to model the fission gas release between 600°C and 800°C on UO$_2$ irradiated fuel.

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

Speciation and release kinetics of the fission products Mo, Cs, Ba and I from nuclear fuels in severe accident conditions

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

Using laser remote heating to simulate extreme thermal loads on nuclear fuels

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

Oxide phase characterization in simulated high burn-up UO$_2$ fuels in the early stages of a nuclear severe accident

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

New Insight on Volatile Fission Products (I and Cs) release from high burnup UO$_2$ fuel under LOCA type conditions

Shielded Electron Microprobe and some of its main applications in HotlabsCharacterization of MOX irradiated fuels treated at very high temperatures

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

CoreSOAR Core Degradation SOAR Update Status May 2017

Design and implementation of a new gamma spectrometry sighting device for gaseous iodine measurements in the VERDON CET-loop

An innovative Method to study Volatile Fission Products speciation in nuclear fuels under Severe Accident Conditions

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

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

Nuclear fuel behaviour at high temperature new insights from post-test examinations on the VERDON-1 sample

MEXIICO a new equipment to study the pressure impact on the irradiated fuel behavior

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

An auto-catalytic mechanism to explain the fission gas release between 500°c and 800°c on UO$_2$ irradiated fuel

Implementation of a new gamma spectrometer on the MERARG loop Application to the volatile fission products release measurement.

Charge distribution in doped uranium dioxide

Main outcomes relative to iodine behaviour from the VERDON/ISTP programme

Use of model materials for fission products release study in Severe Accident Conditions

Increasing of MERARG Experimental Performances On-line Fission Gas Release Measurement by Mass Spectrometry

Fission products behaviour in UO2 submitted to nuclear severe accident conditions

Size and radial origin of fragments formed while heating a 83 GWd/t$_U$ PWR fuel up to 1200 °C

About nuclear fuels on MARS

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

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

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

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

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

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

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

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