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Gerald Rimpault
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A full reference APOLLO3$^®$ deterministic scheme for the JHR material testing reactorPHYSOR 2020 - Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom
Communication dans un congrès
cea-02972474v1
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HPRL – International cooperation to identify and monitor priority nuclear data needs for nuclear applications2019 International Conference on Nuclear Data for Science and Technology, May 2019, Beijing, China. ⟨10.1051/epjconf/202023915005⟩
Communication dans un congrès
hal-02564597v1
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NEA SFR subassembly benchmark sensitivity/uncertainty propagation with depletionBEPU 2018 (ANS Best Estimate Plus Uncertainty International Conference), May 2019, Lucca, Italy
Communication dans un congrès
cea-02400194v1
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Analysis of the feedback coefficients of the Superphenix start-up core with APOLLO3ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France
Communication dans un congrès
cea-02394071v2
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Validation of an advanced APOLLO3® deterministic scheme for characterizing of the Jules Horowitz irradiation reactor coreInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (MandC - 2019)andC2019, Aug 2019, Portland, United States
Communication dans un congrès
cea-02614135v1
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Integral data assimilation on U235 and U238 nuclear data and impact on fca-ix spectral indices to reassess minor actinides fission cross sectionsPHYSOR 2018 Reactors Physics paving the way towards more efficient systems, Apr 2018, Mexique, Cancun, Mexico
Communication dans un congrès
hal-02416214v1
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looking forward for a masurca experimental programme genesis in support to the astrid sfr corePHYSOR 2018 Reactors Physics paving the way towards more efficient systems, Apr 2018, Cancun, Mexico
Communication dans un congrès
hal-02416226v1
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Current Status and Perspectives of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018), May 2018, Lucca, Italy
Communication dans un congrès
cea-02339103v1
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Assessing the Uncertainty of Reactivity Worth Scale MeasurementsNENE 2018 - International Conference on Nuclear Energy for New Europe, Sep 2018, Portoroz, Slovenia
Communication dans un congrès
cea-02338740v1
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a new approach for analysing the impact of nuclear data uncertainties on the astrid sodium void reactivity effectPHYSOR 2018 Reactors Physics paving the way towards more efficient systems, Apr 2018, Cancun, Mexico
Communication dans un congrès
hal-02416227v1
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Integral Experiment Analyses in support to the OECD/NEA benchmarks on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)NENE 2018 - The 27th International Conference Nuclear Energy for New Europe, Sep 2018, Portoroz, Slovenia
Communication dans un congrès
cea-02338749v1
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Accurate reactivity effects of pwr control rods using apollo3 advanced solversPHYSOR 2018, Apr 2018, Cancun, Mexico
Communication dans un congrès
hal-02415315v1
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Apollo3 homogenization techniques for transport core calculations - application to the astrid cfv coreMandC 2017 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Apr 2017, Jeju, South Korea
Communication dans un congrès
hal-02419626v1
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The APOLLO3 scientific tool for SFR neutronic characterization current achievements and perspectivesInternational conference on fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17), Jun 2017, Ekaterinaburg, Russia
Communication dans un congrès
hal-02419657v1
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Objectives and status of the oecd/nea sub-group on uncertainty analysis in modelling (uam) for design, operation and safety analysis of sfrs (sfr-uam)International Conference on Fast Reactors and Related Fuel Cycles (FR - 2017), Jun 2017, Kyoto, Japan
Communication dans un congrès
hal-02419676v1
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A New Breakdown Methodology To Estimate Neutronic Model Biases Applied To Apollo3 SFR Core CalculationsM&C 2017 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Apr 2017, Jeju, South Korea
Communication dans un congrès
cea-02434517v1
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Improvement of minor actinides transmutation performances in fast reactors using fissile materialICAPP17, Apr 2017, Kyoto and Fukui, Japan
Communication dans un congrès
cea-02435080v1
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New Reference APOLLO3 Calculation Scheme for Sodium Cooled Fast Reactors from Sub-Assembly to Full-Core CalculationsPHYSOR2016 - Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States
Communication dans un congrès
hal-02442247v1
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A search for theories enabling analyses of spatial effects in highly coupled sfr coresPHYSOR 2016: Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States. pp.ISBN: 978-0-89448-726-2
Communication dans un congrès
cea-02431806v1
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Analysis and optimization of minor actinides transmutation blankets with regards to neutron and gamma sources13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society -2016 (RPSD-2016), Oct 2016, Paris, France. pp.05005, ⟨10.1051/epjconf/201715305005⟩
Communication dans un congrès
hal-01645305v1
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Uncertainty quantification of delayed neutron fraction of u235 based fuel coresPHYSOR 2016 - The Physics of Reactors conferences: Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States
Communication dans un congrès
cea-02442369v1
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Performance study of a parallel domain decomposition methodPHYSOR 2016 - International Conference on the Physics of Reactors: Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States
Communication dans un congrès
hal-02442270v1
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Pre-design of a target assembly for minor actinides transmutation14th Exchange Meeting on partitioning and transmutation - Actinide and Fission Product Partitioning and Transmutation, Oct 2016, San Diego, United States
Communication dans un congrès
hal-02441960v1
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Analysis of material buckling experiments performed in the masurca facility in support of the astrid sfr prototype core balancePHYSOR 2016 - The Physics of Reactors conferences: Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States
Communication dans un congrès
cea-02442354v1
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An in-depth analysis of Minor Actinide Fission Chambers Measurements in the FCA IX Experimental Programme.ND2016, Joint Research Centre, European Commission, Sep 2016, Bruges, Belgium
Communication dans un congrès
cea-02438371v1
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A domain decomposition method in APOLLO3$^R$ solver, MINARETANS MC2015 - Joint International Conference on Mathematics and Computation (MandC), Supercomputing in Nuclear Applications (SNA) and theMonte Carlo (MC) Method, Apr 2015, Nashville, United States
Communication dans un congrès
cea-02509075v1
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Evaluation of SFR Deformed Core ReactivityICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France
Communication dans un congrès
cea-02933399v1
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Achievements and lessons learned within the Domain 1 "DESIGN" of the IP_EUROTRANS Integrated ProjectFirst International Workshop on Technology and Components of Accelerator-driven Systems, Mar 2010, Karksruhe, Germany. ⟨10.1787/9789264117297-en⟩
Communication dans un congrès
in2p3-00687046v1
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The GUINEVERE project at the VENUS facilityInternational Conference on the Physics of Reactors - PHYSOR 2008, Sep 2008, Interlaken, Switzerland. pp.14-19
Communication dans un congrès
in2p3-00305892v1
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Fine 3D neutronic characterization of a gas-cooled fast reactor based on plate-type subassembliesPHYSOR-2006, ANS Topical Meeting on Reactor Physics, Canadian Nuclear Society, Sep 2006, VANCOUVER, Canada
Communication dans un congrès
cea-02917645v1
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DM1 DESIGN: Development of a Detailed Design of XT-ADS and of a Conceptual Design of EFIT with Heavy Liquid Metal CoolingActinide and Fission Product Partitioning and Transmutation Ninth Information Exchange Meeting, Sep 2006, Nimes, France. pp.433-441
Communication dans un congrès
in2p3-00290526v1
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Neutronic benchmark on the 2400 MW gas-cooled fast reactor designPHYSOR-2006, ANS Topical Meeting on Reactor Physics, Canadian Nuclear Society, Sep 2006, VANCOUVER, Canada
Communication dans un congrès
cea-02917649v1
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Methodology for a Large Gas-Cooled Fast Reactor Core Design and Associated Neutronic UncertaintiesPHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Apr 2004, Chicago, Illinois, United States
Communication dans un congrès
cea-02917618v1
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BN-600 Full MOX Core Benchmark AnalysisPHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, American Nuclear Society, Apr 2004, Chicago, Illinois, United States
Communication dans un congrès
cea-02917608v1
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Dynamic Measurements and Control of an Accelerator Driven System (ADS)PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, Oct 2002, Seoul, South Korea
Communication dans un congrès
cea-02906378v1
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Foil activation studies of spectral variations in the MUSE4 critical configurationPHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, Oct 2002, Seoul, South Korea
Communication dans un congrès
cea-02907055v1
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BN-600 Hybrid core benchmark analysesPHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, Oct 2002, Seoul, South Korea
Communication dans un congrès
cea-02906391v1
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Analyses of experiments in the JOYO fast reactor using the ERANOS and JNC code systemsPHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance, Oct 2002, Seoul, South Korea
Communication dans un congrès
cea-02907166v1
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The ERANOS Code and data system for fast reactor neutronic analysesPHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, Oct 2002, Seoul, South Korea
Communication dans un congrès
cea-02906396v1
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Experimental investigation of multiplying subcritical media coupled with an accelerator : the MUSE experimentsInternational Conference on Emerging Nuclear Energy Systems 10, Sep 2000, Petten, Netherlands. pp.88-97
Communication dans un congrès
in2p3-00012489v1
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Experimental investigation of multiplying subcritical media in presence of an external source operating in pulsed or continuous mode : the MUSE-3 experimentInternational Conference on Accelerator Driven Transmutation Technologies and Applications 3 ADTTA'99, Jun 1999, Praha, Czech Republic. pp.10
Communication dans un congrès
in2p3-00004826v1
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UNCERTAINTIES ASSOCIATED TO THE USE OF THE ERANOS CODE SYSTEM WHEN APPLIED TO THE MODERATED ECRIX IRRADIATIONS IN THE FAST REACTOR PHENIX2020
Pré-publication, Document de travail
cea-02906384v1
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General Synthesis Report of the Different ADS Design Status. Establishment of a Catalogue of the R&D needs[Contract] EURATOM. 2010
Rapport
hal-01084509v1
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