
Vincent PASCAL
19
Documents
Publications
Publications
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Development and first application of a simplified tool for the design of a molten salt reactorNureth 20 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2023, Washington, France. pp.3276-3289, ⟨10.13182/NURETH20-40196⟩
Communication dans un congrès
cea-04696451
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Study of the ARAMIS molten salt reactor behavior during unprotected transients2023 International Congress on Advances in Nuclear Power Plants, in conjunction with 38th Korea Atomic Power Annual Conference (ICAPP 2023 / KAP Conference), Apr 2023, Gyeongju, South Korea. pp.2023200
Communication dans un congrès
cea-04399511
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Multiphysics modelisation of an unprotected loss of flow transient in a sodium cooled fast reactors using a neutronic-thermal-hydraulic coupling schemePHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, Mar 2020, Cancelled, United Kingdom. pp.07001, ⟨10.1051/epjconf/202124707001⟩
Communication dans un congrès
cea-04503531
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Impact of neutronics parameters in a loss-of-flow transient simulation of a low-void sodium-cooled nuclear reactorM&C 2019, 2019, Portland, United States
Communication dans un congrès
hal-02411093
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Validation of LWR Reactivity versus Reactor Period. Feedback on the Delayed Neutron Data (beta i, lambda i)PHYSOR2018: Reactor Physics paving the way towards more efficient systems, Apr 2018, Cancun, Mexico
Communication dans un congrès
hal-02416252
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CATHARE3 transient analysis of an innovative Power Conversion System based on the Brayton cycle modelled with real gas Equations Of StateICAPP, Apr 2018, Charlotte, United States
Communication dans un congrès
cea-02339338
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Phenix: Interpretation Of Ecrix-H Transmutation Experiment With Tripoli4DM&C - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Apr 2017, Jeju-Si, South Korea
Communication dans un congrès
cea-02434521
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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-02419657
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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-02419626
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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-02434553
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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-02442247
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Experimental validation of the new code package APOLLO3-SFR against ZPPR-10A experiment for critical and voided configurationsPHYSOR 2016 - International Conference on the Advances in Reactor Physics Unifying Theory and Experiments in the 21st Century, May 2016, Sun Valley, United States
Communication dans un congrès
hal-02442242
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Analysis of the trapu and doublon irradiations in phenix for the experimental validation of the darwin package for fast reactorsGlobal 2015 - 21st International Conference & Exhibition: " Nuclear Fuel Cycle for a Low-Carbon Future", Sep 2015, Paris, France
Communication dans un congrès
cea-02509740
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