 
    Vincent PASCAL
                                    21 
                                    
                            Documents
                                Publications
Publications
| Decay heat calculations and application of the lines of defence method to Chloride Molten Salt Reactor ARAMIS-AInternational Congress on Advances in Nuclear Power Plants (ICAPP2025), SFEN, Sep 2025, Antibes-Juan Les Pins, FranceCommunication dans un congrès
                    
        
        
            
                
                    in2p3-05175443
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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.2023200Communication 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 StatesCommunication 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, MexicoCommunication 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 StatesCommunication 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 KoreaCommunication 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, RussiaCommunication 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 KoreaCommunication 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 KoreaCommunication 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 StatesCommunication 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 StatesCommunication 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, FranceCommunication dans un congrès
                    
        
        
            
                
                    cea-02509740
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| Benchmark calculations on control rod withdrawal tests performed during phenix end-of-life experimentsICAPP 2013 - International Congress on Advances in Nuclear Power Plants; 28. KIF/KNS annual conference, Korean Nuclear Society (KNS / KAIF), Apr 2013, Jeju Island, South Korea. pp.408-418Communication dans un congrès
                    
        
        
            
                
                    hal-05175359
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