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Bastien Faure
Bastien Faure
在 cea.fr 的电子邮件经过验证
标题
引用次数
引用次数
年份
APOLLO3 homogenization techniques for transport core calculations—application to the ASTRID CFV core
JF Vidal, P Archier, B Faure, V Jouault, JM Palau, V Pascal, G Rimpault, ...
Nuclear Engineering and Technology 49 (7), 1379-1387, 2017
452017
Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation
H Guo, E Garcia, B Faure, L Buiron, P Archier, P Sciora, G Rimpault
Annals of Nuclear Energy 129, 90-100, 2019
232019
Neutronic calculation of an axially heterogeneous ASTRID fuel assembly with APOLLO3®: Analysis of biases and foreseen improvements
B Faure, P Archier, JF Vidal, JM Palau, L Buiron
Annals of Nuclear Energy 115, 88-104, 2018
232018
A 2D/1D algorithm for effective cross-section generation in fast reactor neutronic transport calculations
B Faure, P Archier, JF Vidal, L Buiron
Nuclear Science and Engineering 192 (1), 40-51, 2018
192018
A comparison of actinide halides for use in molten salt reactor fuels
B Faure, T Kooyman
Progress in Nuclear Energy 144, 104082, 2022
152022
Simulation of a sodium fast core: Effect of B1 leakage models on group constant generation
B Faure, G Marleau
Annals of Nuclear Energy 99, 484-494, 2017
92017
Simulation des fuites neutroniques à l'aide d'un modèle B1 hétérogène pour des réacteurs à neutrons rapides et à eau légère
B Faure
Ecole Polytechnique, Montreal (Canada), 2016
72016
3-D analysis of the UH1. 2 mock-up experiment using the Apollo3 IDT method and comparisons against Tripoli4 Monte-Carlo reference calculations
JM Palau, JF Vidal, P Archier, B Faure, E Masiello
62018
Flux distribution of the Superphénix start-up core for the validation of neutronic codes
E Garcia, P Sciora, T Kooyman, G Rimpault, H Guo, B Faure
Annals of Nuclear Energy 133, 889-899, 2019
42019
Development and Verification of Perturbative Methods in the APOLLO3 Code: Sensitivity Analysis and Uncertainty Quantification Applied to Pressurized-Water and Sodium Fast Reactors
P Archier, A Calloo, G Valocchi, B Faure, JM Palau
Proceedings of M&C, 2019
32019
Impact of neutronics parameters in a loss-of-flow transient simulation of a low-void sodium-cooled nuclear reactor
B Faure, P Archier, G Valocchi, L Buiron, J Droin, V Pascal
M&C 2019, 2019
22019
recent progess in the vetv of the french apollo3 code 3d full core analysis of the uh1. 2 integral experiment using idtmethod of characteristics
J Palau, E Masiello, J Vidal, P Archier, B Faure
PHYSOR 2018, 2018
22018
Methods and systems for automated optimization of COx electrolysis reactor
B Faure, S Lamaison, D Wakerley
US Patent 11,519,089, 2022
12022
IMPACT OF NEUTRONIC PARAMETERS IN A LOSS–OF–FLOW TRANSIENT SIMULATION OF A LOW VOID REACTIVITY SODIUM–COOLED NUCLEAR REACTOR
B Faure, P Archier, P Sciora, G Valocchi, L Buiron, J Droin, V Pascal, ...
Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear …, 2019
12019
Development of neutronic calculation schemes for heterogeneous sodium-cooled nuclear cores in the Apollo3® code: application to the ASTRID prototype
B Faure
Universite d'Aix-Marseille, 2019
12019
A 2D/1D Method for Consistent Burnup Parametrization of Cross Sections in SFR Fuel Depletion Calculations
B Faure, P Archier, L Buiron
PHYTRA4-The Fourth International Conference on Physics and Technology of …, 2018
12018
Methods and systems for automated optimization of cox electrolysis reactor
B Faure, S Lamaison, D Wakerley
US Patent App. 18/292,021, 2024
2024
Reactors and Methods for Production of Sustainable Chemicals using Carbon Emissions of Metallurgical Furnaces
RG Mariano, S Lamaison, J Maistrello, D Wakerley, A Ozden, B Faure, ...
US Patent App. 18/208,245, 2024
2024
Reactors and Methods to Reduce Carbon Footprint of Electric Arc Furnaces While Producing Sustainable Chemicals
S Lamaison, J Maistrello, RG Mariano, B Faure, D Wakerley, L Leveen
US Patent App. 18/138,116, 2024
2024
CEA CADARACHE
B FAURE
École Polytechnique de Montréal, 2019
2019
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