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52 résultats
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Spatial analysis of unprotected transients in heterogeneous sodium fast reactorsAnnals of Nuclear Energy, 2018, 115, pp.554-564. ⟨10.1016/j.anucene.2018.01.029⟩
Article dans une revue
cea-02421718v1
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Transient Fission Matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurationsAnnals of Nuclear Energy, 2019, 128, pp.390-397. ⟨10.1016/j.anucene.2019.01.031⟩
Article dans une revue
cea-02510825v1
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Preliminary design studies of the draining thanks for the molten salt fast reactorEuropean Nuclear Conference (ENC 2014), May 2014, Marseille, France. pp.220-230
Communication dans un congrès
in2p3-00990875v1
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Viability limits of the renewable source in an electricity mix: The MIXOPTIM analysis methodologyThe European Physical Journal Plus, 2019, 134 (12), pp.614. ⟨10.1140/epjp/i2019-12942-1⟩
Article dans une revue
hal-02409818v1
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MIXOPTIM : A tool for the evaluation and the optimization of the electricity mix in a territoryThe European Physical Journal Plus, 2014, 129 (9), pp.198. ⟨10.1140/epjp/i2014-14198-7⟩
Article dans une revue
cea-01089278v1
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The role of power sources in the European electricity mixEPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.10. ⟨10.1051/epjn/e2015-50012-0⟩
Article dans une revue
in2p3-01501222v1
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Identification and study of incidental and accidental scenarios for the molten salt fast reactor4th International Conference on Physics and Technology of Reactors and Applications (PHYTRA4), Sep 2018, Marrakech, Morocco
Communication dans un congrès
hal-01879706v1
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Concept of the Molten Salt Fast Reactor (MSFR) developed at CNRS in FranceTechnical Meeting on the Status of Molten Salt Reactor Technology, Oct 2016, Vienna, Austria
Communication dans un congrès
in2p3-01404131v1
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Coupled neutronics and thermal-hydraulics transient calculations based on a fission matrix approach: application to the molten salt fast reactorJoint International Conference on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method (M&C + SNA + MC 2015), Apr 2015, Nashville, United States
Communication dans un congrès
in2p3-01176258v1
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Transient coupled calculations of the Molten Salt Fast Reactor using the Transient Fission Matrix approachNuclear Engineering and Design, 2017, 316, pp.112-124. ⟨10.1016/j.nucengdes.2017.02.022⟩
Article dans une revue
in2p3-01494272v1
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Outils de calculs de transitoire du MSFR : comparaison et benchmarkAtelier Sûreté-MSFR (NEEDS PF Systèmes Nucléaires et Scénarios), Nov 2014, Grenoble, France
Communication dans un congrès
in2p3-01085864v1
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Towards spatial kinetics in a low void effect sodium fast reactor: core analysis and validation of the TFM neutronic approachEPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.17. ⟨10.1051/epjn/2017008⟩
Article dans une revue
cea-02304291v1
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A methodology for the identification of the postulated initiating events of the Molten Salt Fast ReactorNuclear Engineering and Technology, 2019, 51 (4), pp.1024-1031. ⟨10.1016/j.net.2019.01.009⟩
Article dans une revue
hal-02154328v1
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Design evolutions of Molten Salt Fast Reactornternational Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systemes for Sustainable Development (FR17), Jun 2017, Yekaterinburg, Russia
Communication dans un congrès
in2p3-01572660v1
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The role of nuclear power in the european energy mixInternational Congress on Advances in Nuclear Power Plants “Nuclear Innovations for a Low-Carbon Future” (ICAPP 2015), May 2015, Nice, France. pp.3088-3093
Communication dans un congrès
in2p3-01150850v1
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Outils de simulation et calculs de transitoires du MSFRAtelier Sûreté-MSFR (NEEDS PF Systèmes Nucléaires et Scénarios), Oct 2015, Fontenay aux Roses, France
Communication dans un congrès
in2p3-01217923v1
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Progress on MSR pSSC activities, GIF MSRProgress on MSR pSSC activities, GIF MSR, Oct 2018, Paris, France
Communication dans un congrès
hal-02412916v1
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A passive decay heat removal system for emergency draining tanks of molten salt reactorsNuclear Engineering and Design, 2019, 341, pp.423-431. ⟨10.1016/j.nucengdes.2018.11.021⟩
Article dans une revue
hal-01952716v1
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Outils de calculs de transitoire du MSFR : approche des matrices de fissionAtelier Sûreté-MSFR (NEEDS PF Systèmes Nucléaires et Scénarios), Nov 2014, Grenoble, France
Communication dans un congrès
in2p3-01085850v1
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The LiCore power plant simulator of the molten salt fast reactorInternational Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.06030, ⟨10.1051/epjconf/202124706030⟩
Communication dans un congrès
hal-03325769v1
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Transient Fission Matrix: Kinetic calculation and kinetic parameters βeff and Λeff calculationAnnals of Nuclear Energy, 2015, 85, pp.1035-1044. ⟨10.1016/j.anucene.2015.07.023⟩
Article dans une revue
in2p3-01214500v1
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French R&D Activities Progress Summary, GIF MSRGIF MSR pSSC, IAEA Vienna, Sep 2017, Vienne, Austria
Communication dans un congrès
hal-02412914v1
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Tool developments in the OpenMC code: Correlated Sampling and Transient Fission Matrix approach using OpenFOAM CFD meshM&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Aug 2023, Niagara Falls, Canada
Communication dans un congrès
hal-04298512v1
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First in-core gamma spectroscopy experiments in a zero power reactorEPJ Web of Conferences, 2021, 253, pp.04022. ⟨10.1051/epjconf/202125304022⟩
Article dans une revue
hal-03869627v1
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Fission Matrix Interpolation For The Tfm Approach Based On A Local Correlated Sampling Technique For Fast Spectrum Heterogeneous ReactorsM&C - 2017 International Meeting on Mathematics and Computation Supercomputing, Reactor Physics and Nuclear and Biological Applications, Apr 2017, Jeju, South Korea
Communication dans un congrès
cea-02434553v1
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Transient coupled neutronics-thermalhydraulics study of ULOF accidents in sodium fast reactors using spatial kinetics: comparison of the TFM Monte Carlo and SN approachesInternational Congress on Advances in Nuclear Power Plants (ICAPP - 2017), Apr 2017, Fukui-Kyoto, Japan
Communication dans un congrès
cea-02434560v1
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Local correlated sampling Monte Carlo calculations in the TFM neutronics approach for spatial and point kinetics applicationsEPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.16. ⟨10.1051/epjn/2017011⟩
Article dans une revue
cea-02305849v1
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Preliminary proliferation study of the molten salt fast reactorEPJ N - Nuclear Sciences & Technologies, 2020, 6, pp.5. ⟨10.1051/epjn/2019062⟩
Article dans une revue
hal-03037616v1
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Viability limits of the renewable source in an electricity mix: Application to the French mix with anamorphic evolutionsThe European Physical Journal Plus, 2019, 134 (12), pp.615. ⟨10.1140/epjp/i2019-12941-2⟩
Article dans une revue
hal-02409816v1
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A closed fuel cycle option using the MSFR concept with chloride salts and the U/Pu cycleGLOBAL 2022: International Conference on Nuclear Fuel Cycle | New nuclear perspectives in the energy supply crisis and climate emergency, SFEN, Jul 2022, Reims, France. ⟨10.5281/zenodo.7323019⟩
Communication dans un congrès
hal-04299709v1
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