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A Simple Modeling for Gas Release During Annealing of Irradiated Nuclear FuelTransactions of the American Nuclear Society, 2023, 128 (1), pp.404-407
Article dans une revue
hal-04459527v1
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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?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
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Influence of the miscibility gap in the evolution of the microstructure in UO2-based fuel doped with Nd2019 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
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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.MRS spring 2018, Apr 2018, Phoenix, United States
Communication dans un congrès
cea-02339066v1
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An auto-catalytic mechanism to model the fission gas release between 600°C and 800°C on UO2 irradiated fuelMRS 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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Thin film samples: a new methodology for investigating the mechanisms of fission gas releases from nuclear fuel during a LOCA2016 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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An auto-catalytic mechanism to explain the fission gas release between 500°c and 800°c on UO$_2$ irradiated fuelNumat2016, Nov 2016, Montpellier, France
Communication dans un congrès
cea-02437063v1
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Charge distribution in doped uranium dioxide45èmes 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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Influence of the miscibility gap in the evolution of the microstructure in UO2-based fuel doped with NdMatériaux 2018. Colloque 14 – Matériaux en environnements extrêmes, Nov 2018, Strasbourg, France
Poster de conférence
hal-01933127v1
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An auto-catalytic mechanism to model the fission gas release between 500°C and 800°C on UO2 irradiated fuelPoster de conférence hal-01480689v1 |