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84 résultats
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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On integrating Monte Carlo calculations in and around near-critical configurations – I. MethodologyAnnals of Nuclear Energy, 2022, 172, pp.109063. ⟨10.1016/j.anucene.2022.109063⟩
Article dans une revue
hal-03706621v1
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TEX-MOX experiments: final design of critical experiments to mimic MOX fuel in low moderation conditions2024 Fall Meeting of Atomic Energy Society of Japan, Sep 2024, Sendai (Japan), Japan
Communication dans un congrès
hal-04740696v1
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Analysis of a VVER-1000 in-core fuel management benchmark with DRAGON and DONJONInternational Journal of Nuclear Energy Science and Technology, 2017, 11, pp.345--376. ⟨10.1504/IJNEST.2017.090658⟩
Article dans une revue
hal-02940141v1
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AN ALTERNATIVE SIMPLE APPROACH FOR THE MODELLING OF FUEL ASSEMBLIES WITH MISSING FUEL RODS11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02635614v1
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Impact of core power variations on the fast neutron flux incident on pressurized water reactor vesselsInternational Congress on Advances in Nuclear Power Plants (ICAPP 2019), May 2019, JUAN LES PINS, France
Communication dans un congrès
hal-02463775v1
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Subcritical Copper-Reflected α-phase Plutonium (SCRαP) Measurements and SimulationsM&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, American Nuclear Society, Apr 2017, Jeju, South Korea
Communication dans un congrès
hal-04122068v2
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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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PyNjoy2016: an Open Source System for Producing Cross Sections Libraries for DRAGON5 and SERPENT2M&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-04095482v2
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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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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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Contribution to the validation of the MORET 5 code using the CROCUS reactor physics benchmarkAnnals of Nuclear Energy, 2021, 155, pp.1-12. ⟨10.1016/j.anucene.2021.108164⟩
Article dans une revue
hal-03202427v1
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Application of the SPH equivalence technique to the CABRI full core in non-fundamental modePHYSOR 2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear, American Nuclear Society, Mar 2020, Cambridge, United Kingdom. pp.03019, ⟨10.1051/epjconf/202124703019⟩
Communication dans un congrès
irsn-04106635v1
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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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Comparison of two methods for assessment of the rod positioning uncertainty and consequences on the evaluation of correlation factorsFrontiers in Energy Research, 2022, 10, ⟨10.3389/fenrg.2022.1058750⟩
Article dans une revue
irsn-04122111v1
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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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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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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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PIN POWER CALCULATION SCHEME FOR REACTOR PRESSURE VESSEL FAST NEUTRON FLUENCE ESTIMATIONPHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, France. pp.02029, ⟨10.1051/epjconf/202124702029⟩
Communication dans un congrès
irsn-04666996v1
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Integral experiments at Sandia with molybdenum sleeves for testing 95Mo cross sections in thermal energy spectrumNuclear Criticality Safety Division Topical Meeting (NCSD) 2022, Jun 2022, ANAHEIM, United States
Communication dans un congrès
hal-03738265v1
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THE OXNIT DENSITY LAW IN CRISTAL PACKAGE: AN EASY WAY TO PREDICT THE COMPOSITION OF DISSOLVED OXIDE IN NITRATE SOLUTIONS11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02507249v1
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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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Nuclear Data Uncertainties and Adjustments Using Deterministic and Monte-Carlo Methods along with PWR MeasurementsM&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-04095487v2
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The princess project: from differential to integral experimentsInternational Conference on Physics of Reactors: Transition to a Scalable Nuclear Future PHYSOR2020, Mar 2020, Cambridge, United Kingdom. pp.1-8, ⟨10.1051/epjconf/202124720002⟩
Communication dans un congrès
hal-04123100v2
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Evaluation of thermal scattering law for light water based on new time-of-flight measurements at the Institute Laue-Langevin (ILL)PHYTRA4 - The 4th International Conference on Physics and Technology of Reactors and Applications, Sep 2018, Marrakech, Morocco
Communication dans un congrès
hal-02377307v1
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Criticality configuration design methodology applied to the design of fuel debris experiment in the new STACYJournal of Nuclear Science and Technology, 2021, ⟨10.1080/00223131.2020.1798825⟩
Article dans une revue
hal-03013234v1
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Similarity of the PMM-2 critical experiments and criticality safety cases based on the keff sensitivity analysisANS Winter Meeting and nuclear technology, Nov 2021, WASHINGTON, United States
Communication dans un congrès
hal-03482397v1
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RESONANCE EVALUATION OF 239PU IN THE RESONANCE REGION UP TO 4 KEV2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, Mar 2020, Cambridge, United Kingdom. pp.1755 - 1761, ⟨10.1051/epjconf/202124709006⟩
Communication dans un congrès
hal-03465837v1
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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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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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