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56 résultats
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triés par
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The Impact of Reactor Model Simplification for Fuel Evolution: A Bias Quantification for Fuel Cycle Dynamic Simulations2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), Apr 2016, San Francisco, United States. pp.1045-1053
Communication dans un congrès
in2p3-01346740v1
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Measurements of the mass and isotopic yields of the 233U(n,f) and 241Pu(n,f) reactions at the Lohengrin spectrometerSecond International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), Jun 2011, Ghent, Belgium. pp.1-7, ⟨10.1109/ANIMMA.2011.6172920⟩
Communication dans un congrès
in2p3-00600421v1
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Reactivity monitoring using the area method for the subcritical VENUS-F core within the framework of the FREYA ProjectInternational Workshop on Technology and Components of Accelerator Driven Systems (TCADS) OECD Nuclear Energy Agency, 2013, Nantes, France. pp.88-97
Communication dans un congrès
in2p3-00829301v1
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Influence de l'unité de retraitement sur le comportement d'un TMSRRencontres Jeunes Chercheurs 2008. Physique et Chimie Nucléaires : du Fondamental aux Applications !, Jan 2009, Les Houches, France
Communication dans un congrès
in2p3-00351602v1
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Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unitAnnals of Nuclear Energy, 2013, 64, pp.430-440. ⟨10.1016/j.anucene.2013.09.009⟩
Article dans une revue
in2p3-00908811v1
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Assessment of strategy robustness under disruption of objective in dynamic fuel cycle studiesAnnals of Nuclear Energy, 2021, 154, pp.108131. ⟨10.1016/j.anucene.2021.108131⟩
Article dans une revue
hal-03162259v1
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Current progress and future plans of the FREYA ProjectInternational Workshop on Technology and Components of Accelerator Driven Systems (TCADS) OECD Nuclear Energy Agency, May 2013, Nantes, France. pp.78-87
Communication dans un congrès
in2p3-00829300v1
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Thorium Molten Salt Fast Reactor Nuclear Data Uncertainty AnalysisInternational Conference on Nuclear Data for Science and Technology (ND2010), Apr 2010, Jeju Island, South Korea
Communication dans un congrès
in2p3-00485584v1
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Reactor physic and reprocessing scheme for innovative molten salt reactor systemJournal of Fluorine Chemistry, 2009, 130, pp.11-17. ⟨10.1016/j.jfluchem.2008.07.009⟩
Article dans une revue
istex
in2p3-00355091v1
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MOX fuel enrichment prediction in PWR using polynomial modelsAnnals of Nuclear Energy, 2015, 85, pp.812-819. ⟨10.1016/j.anucene.2015.06.038⟩
Article dans une revue
in2p3-01189018v1
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Validation of the Nodal Drift Method on a CANDU LOCA and First Application to the TWIGL Seed-Blanket REAInternational Congress on Advances in Nuclear Power Plants (ICAPP 2016), Apr 2016, San Francisco, United States. pp.2148-2157
Communication dans un congrès
in2p3-01376565v1
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An alternative source Jerk method implementation for the subcriticality estimation of the Venus-F subcritical core in the FREYA projectANIMMA 2013 - Avancements in Nuclear Instrumentation Measurement Methods and their applications, 2013, Marseille, France
Communication dans un congrès
in2p3-00840020v1
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Monte Carlo MSM Correction Factors for Control Rod Worth Estimates in Subcritical and Near-Critical Fast Neutron Reactors2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015), May 2015, Nice, France. pp.1733-1742
Communication dans un congrès
in2p3-01144633v1
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Mean cross section prediction in PWR-MOX using neural networkNuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015), Sep 2015, Paris, France. pp.840-846
Communication dans un congrès
in2p3-01247904v1
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Simulation tools and new developments of the molten salt fast reactorRevue Generale Nucleaire, 2010, 6, pp.95-100. ⟨10.1051/rgn/20106095⟩
Article dans une revue
in2p3-00561186v1
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Optimization and simplification of the concept of non-moderated Thorium Molten Salt ReactorInternational Conference on the Physics of Reactors - PHYSOR 2008, Sep 2008, Interlaken, Switzerland
Communication dans un congrès
in2p3-00326466v1
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Neutronic predictors for PWR fuelled with multi-recycled plutonium and applications with the fuel cycle simulation tool CLASSProgress in Nuclear Energy, 2017, 100, pp.33-47. ⟨10.1016/j.pnucene.2017.04.018⟩
Article dans une revue
in2p3-01534704v1
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Numerical tools for molten salt reactors simulationInternational Conference GLOBAL 2009 "The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives", Sep 2009, Paris, France. pp.1631-1639
Communication dans un congrès
in2p3-00422496v1
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Le réacteur à sels fondus MSFRV. Ghetta, J. Fouletier, P. Taxil. Sels fondus à haute température, Presses Polytechniques et Universitaires Romandes, pp.241-254, 2009
Chapitre d'ouvrage
in2p3-00441649v1
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DONJON5/CLASS coupled simulations of MOX/UO$_2$ heterogeneous PWR coreTechnical Workshop on Fuel Cycle Simulation 2021, Jun 2021, Online, France. pp.4, ⟨10.1051/epjn/2021030⟩
Communication dans un congrès
hal-03617223v1
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Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulationsAnnals of Nuclear Energy, 2019, 128, pp.69-76. ⟨10.1016/j.anucene.2018.12.037⟩
Article dans une revue
hal-01975524v1
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Nuclear and renewables in deregulated markets. Nuclear fuel cycle cost estimates with cross-disciplinary modelling3rd technical workshop on fuel cycle simulation, Jul 2018, Paris, France
Communication dans un congrès
hal-01838422v1
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Study of Argentinian and Brasilian Nuclear Symbiotic Scenarios using CLASSInternational Congress on Advances in Nuclear Power Plants (ICAPP 2016), Apr 2016, San Francisco, United States. pp.2032-2039
Communication dans un congrès
in2p3-01347446v1
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Measurements of the Mass and Isotopic Yields of the 233U(nth,f) Reaction by the Lohengrin SpectrometerNuclear Data Sheets, 2014, 119, pp.328-330. ⟨10.1016/j.nds.2014.08.090⟩
Article dans une revue
in2p3-01337069v1
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Americium mono-recycling in PWR: A step towards transmutationAnnals of Nuclear Energy, 2017, 102, pp.220 - 230. ⟨10.1016/j.anucene.2016.12.004⟩
Article dans une revue
in2p3-01427447v1
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Validation of the minimalistic Nodal Drift Method for spatial kinetics on a simple CANDU LOCA benchmarkAnnals of Nuclear Energy, 2016, 88, pp.135-150. ⟨10.1016/j.anucene.2015.10.037⟩
Article dans une revue
in2p3-01264675v1
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Core library for advanced scenario simulation, C.L.A.S.S.: principle & applicationInternational Conference “The Role of Reactor Physics toward a Sustainable Future” (PHYSOR 2014), Sep 2014, Kyoto, Japan. PHYSOR 2014 “The Role of Reactor Physics toward a Sustainable Future” CD-ROM, 12 p
Poster de conférence
in2p3-01119778v1
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Monte Carlo MSM correction factors for control rod worth estimates in subcritical and near-critical fast neutron reactorsEPJ N - Nuclear Sciences & Technologies, 2015, 1, pp.2. ⟨10.1051/epjn/e2015-50041-5⟩
Article dans une revue
in2p3-01274914v1
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Analysis of prompt decay experiments for ADS reactivity monitoring at VENUS-F GUINEVERE facilityInternational Workshop on Technology and Components of Accelerator Driven Systems (TCADS-2) OECD Nuclear Energy Agency, 2013, Nantes, France. pp.98-108
Communication dans un congrès
in2p3-00829303v1
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Americium Early Transmutation in Thermal Reactors: An Option to a Better Nuclear Spent Fuel ManagementICAPP 2017 : International Congress on Advances in Nuclear Power Plants, Apr 2017, Kyoto, Japan. pp.17388
Communication dans un congrès
in2p3-01515189v1
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