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39 résultats
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triés par
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Importance of the axial burn-up modelling for fuel assembly nozzles activation calculationInternational Conference on the Physics of Reactors, PHYSOR, May 2022, PITTSBURGH (Virtual), United States
Communication dans un congrès
hal-03746147v1
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Neutronic modeling strategies for a liquid fuel transient calculationInternational Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.06013, ⟨10.1051/epjconf/202124706013⟩
Communication dans un congrès
hal-03325385v1
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Neutronic, thermohydraulic and thermomechanical coupling for the modeling of criticality accidents in nuclear systemsGénie civil nucléaire. Université Grenoble Alpes [2020-..], 2020. English. ⟨NNT : 2020GRALI078⟩
Thèse
tel-03172978v1
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Improving variance estimation for time-dependent detectors in Monte Carlo dynamic calculations using adaptive sampling of neutronsM&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, American Nuclear Society, Aug 2023, Niagara Falls, Ontario, Canada
Communication dans un congrès
irsn-04122131v1
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Design of TEX-MOX critical experiments varying neutron spectrumICNC 2023 - The 12th International Conference on Nuclear Criticality Safety, JAEA, Oct 2023, Sendai, Japan
Communication dans un congrès
hal-04627968v1
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Impact of fission spectrum modeling on aging estimations of Pressurized Water Reactor vessels2021 ANS Winter Meeting and Technology Expo, American Nuclear Society, Nov 2021, Washington, United States
Communication dans un congrès
hal-03525466v1
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Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core ResultsJournal of Nuclear Engineering and Radiation Science, 2021, 8 (1), pp.11301. ⟨10.1115/1.4048905⟩
Article dans une revue
irsn-04122162v3
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Etudes de la convergence d'un calcul Monte Carlo de criticité : utilisation d'un calcul déterministe et détection automatisée du transitoirePhysique Nucléaire Expérimentale [nucl-ex]. Université de Grenoble, 2012. Français. ⟨NNT : 2012GRENY063⟩
Thèse
tel-00846504v1
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Development of a multi-zone fuel loading model for scenario studies involving ASTRID-like SFRs with the CLASS code4th annual Technical Workshop on Fuel Cycle Simulation, TWOFCS19, Jun 2019, Urbana-Champaign, United States
Communication dans un congrès
hal-04125741v1
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Theoretical and Experimental Approach Towards Generation of Thermal Scattering Law for Light WaterTheoretical and/or physical chemistry. Université de Lille, 2018. English. ⟨NNT : 2018LILUR036⟩
Thèse
tel-02390769v1
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Development of a methodology to exploit nuclear data in the unresolved resonance range and the impact on criticality safety and reactor applicationsNuclear Theory [nucl-th]. Université Paris-Saclay, 2020. English. ⟨NNT : 2020UPASP074⟩
Thèse
tel-03168175v1
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Analysis of transition scenario from a PWR to a SFR fleet simulated with the class code14th International Nuclear Fuel Cycle Conference GLOBAL 2019, and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Sep 2019, Seattle, United States. pp.202-211
Communication dans un congrès
hal-04122132v2
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Capteurs à fibres optiques répartis pour la surveillance du corium en cas d'accident grave de réacteur nucléaire avec percement de la cuve : le projet ANR RSNR DISCOMSJNOG 2019 - 39e Journées Nationales d’Optique Guidée, Université Paris-Saclay, Jul 2019, Saclay, France
Communication dans un congrès
cea-04094221v1
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Development Progress of the GAIA nuclear data processing softwareNuclear Data Sheets, 2014, 118 (1), pp.491-493. ⟨10.1016/j.nds.2014.04.115⟩
Article dans une revue
hal-02611868v1
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Measurement of double differential cross-section of light water at high temperature and pressure to generate S(α,β)EPJ Web of Conferences, 2017, 146, pp.13006. ⟨10.1051/epjconf/201714613006⟩
Article dans une revue
hal-01618681v1
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Impact du déploiement de réacteurs de type ASTRID sur la gestion dynamique du plutonium dans des scénarios de transitions électronucléairesPhysique Nucléaire Théorique [nucl-th]. Université Paris Saclay (COmUE), 2019. Français. ⟨NNT : 2019SACLS494⟩
Thèse
tel-02628512v1
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REGAL International Program: Analysis of experimental data for depletion code validationAnnals of Nuclear Energy, 2022, 172, pp.109057. ⟨10.1016/j.anucene.2022.109057⟩
Article dans une revue
irsn-04588935v1
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A Versatile Methodology for Reactor Pressure Vessel Aging AssessmentsNuclear Science and Engineering, 2022, 196 (4), pp.455-477. ⟨10.1080/00295639.2021.1991761⟩
Article dans une revue
hal-03636003v1
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Resonance Parameters and Covariance Evaluations for the Gadolinium Isotopes11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02478476v1
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Isotope studies of the Caspian Sea: Climatic record from the bottom sediments (preliminary results)Internat. Atomic Energy Agency, 1997, pp.1-19
Article dans une revue
hal-04478917v1
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On the use of different variance reduction techniques within MCNP to calculate the flux on the concrete walls of a pressurized water reactorInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), American Nuclear Society (ANS), Aug 2019, Portland (OR), United States. pp.Pages 104-119
Communication dans un congrès
hal-04513231v1
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Development of a multi-zone irradiation model for scenario studies involving ASTRID-like SFRsICAPP 2019 – International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-pins, France
Communication dans un congrès
hal-04125760v1
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An initiative for the development and application of open-source multi-physics simulation in support of R&D and E&T in nuclear science and technologyInternational Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.02040, ⟨10.1051/epjconf/202124702040⟩
Communication dans un congrès
hal-03325387v1
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CRISTAL v2: new package for criticality calculationsNuclear Criticality Safety Division Topical Meeting (NCSD 2017), Sep 2017, Carlsbad, United States
Communication dans un congrès
hal-02417819v1
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Amélioration des simulations Monte Carlo en physique des réacteurs par échantillonnage adaptatif des histoires de neutronsStatistical Mechanics [cond-mat.stat-mech]. Université Paris-Saclay, 2023. English. ⟨NNT : 2023UPASP011⟩
Thèse
tel-04082033v1
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Evaluation of the 235U resonance parameters to fit the standard recommended valuesND 2016 International Conference on Nuclear Data for Science and Technology, EPJ Web of Conferences, Sep 2016, Bruges, Belgium. pp.02021, ⟨10.1051/epjconf/201714602021⟩
Communication dans un congrès
hal-04482694v1
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SYSTEMATIC ANALYSIS OF MULTIVARIATE SCENARIOS USING ADVANCED CLUSTERING METHODSInternational Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.13002, ⟨10.1051/epjconf/202124713002⟩
Communication dans un congrès
hal-03171318v1
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Testing thermal scattering law for light water at 600 k using vesta 2.2.0 depletion calculations11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02463773v1
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Sensitivity of Pressurized Water Reactors Vessels Aging to Fuel CompositionAmerican Nuclear Society (ANS) International Winter Meeting and Nuclear Technology Expo, ANS, Nov 2021, WASHINGTON, United States
Communication dans un congrès
hal-03525465v1
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Improving the variance in Monte Carlo criticality calculations with adaptative multilevel splittingPHYSOR 2022 - International Conference on the Physics of Reactors, American Nuclear Society (ANS), May 2022, Pittsburgh, United States
Communication dans un congrès
irsn-03948886v1
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