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Yannick Gorsse
Yannick Gorsse
CEA Saclay
Verified email at cea.fr
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Cited by
Year
A simple second order cartesian scheme for compressible Euler flows
Y Gorsse, A Iollo, H Telib, L Weynans
Journal of Computational Physics 231 (23), 7780-7794, 2012
492012
A simple Cartesian scheme for compressible multimaterials
Y Gorsse, A Iollo, T Milcent, H Telib
Journal of Computational Physics 272, 772-798, 2014
332014
Development and validation of multi-scale thermal-hydraulics calculation schemes for SFR applications at CEA
A Gerschenfeld, S Li, Y Gorsse, R Lavastre
International Conference on Fast Reactors and Related Fuel Cycles Next …, 2017
232017
An analysis and an affordable regularization technique for the spurious force oscillations in the context of direct-forcing immersed boundary methods
M Belliard, M Chandesris, J Dumas, Y Gorsse, D Jamet, C Josserand, ...
Computers & Mathematics with applications 71 (5), 1089-1113, 2016
172016
Numerical analysis of core thermal-hydraulic for sodium-cooled fast reactors
A Conti, A Gerschenfeld, Y Gorsse, T Cadiou, R Lavastre
NURETH 2015-16th International Topical Meeting on Nuclear Reactor Thermal …, 2015
162015
CFD analysis of the flow in the MICAS experimental facility, a water model of the hot pool of a sodium cooled fast reactor
U Bieder, J Maillard, Y Gorsse, D Guenadou
Nuclear Engineering and Design 350, 67-77, 2019
112019
Multiphysics modelisation of an unprotected loss of flow transient in a sodium cooled fast reactors using a neutronic-thermal-hydraulic coupling scheme
V Pascal, Y Gorsse, N Alpy, K Ammar, M Anderhuber, AM Baudron, ...
EPJ Web of Conferences 247, 07001, 2021
62021
Development of a Polyhedral Staggered Mesh Scheme Application to Subchannel and CFD SFR Thermal Hydraulics
A Gerschenfeld, Y Gorsse, G Fauchet
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019
62019
Thermal-hydraulic analysis of the flow in the MICAS experimental facility using CFD
H Bhatia, U Bieder, Y Gorsse, D Guenadou
Computational fluid dynamics for nuclear reactor safety conference (CFD4NRS …, 2020
42020
Accurate Sharp Interface Scheme for Multimaterials
Y Gorsse, A Iollo, T Milcent, H Telib
Seventh International Conference on Computational Fluid Dynamics (7; 2012 …, 2012
42012
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD
N Greiner, F Madiot, Y Gorsse, C Patricot, G Campioni
Nuclear Science and Engineering 197 (12), 3000-3021, 2023
32023
VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactor
N Marie, S Li, A Marrel, M Marquès, S Bajard, A Tosello, J Perez, ...
EPJ N-Nuclear Sciences & Technologies 7, 3, 2021
32021
A simple second order cartesian scheme for compressible flows
Y Gorsse, A Iollo, L Weynans
Finite Volumes for Complex Applications VI Problems & Perspectives: FVCA 6 …, 2011
32011
Development of a robust multiphase flow solver on general meshes; application to sodium boiling at the subchannel scale
A Gerschenfeld, Y Gorsse
NURETH-19-19th International Topical Meeting on Nuclear Reactor Thermal …, 2022
22022
Prospects for a CEA and ROSATOM/IPPE collaborative program on Na boiling for GEN IV SFRs safety rationale and thermal-hydraulic preparatory work
M Anderhuber, A Gerschenfeld, Y Gorsse, N Alpy, L Christian, ...
NURETH-18, 2019
22019
CFD simulations of selected steady-state and transient experiments in the PLANDTL test facility
S Gurgacz, U Bieder, Y Gorsse, K Swirski
Journal of Physics: Conference Series 745 (3), 032042, 2016
22016
Coupled Neutronics-Thermal-Hydraulic Modeling of a Molten Salt Reactor: The Aircraft Reactor Experiment
F Martin, A Bergeron, G Campioni, Y Gorsse, N Greiner, E Merle
Nuclear Science and Engineering, 1-12, 2024
12024
Preliminary conceptual design of an electronuclear system for space applications
F Bertrand, JB Droin, M Charlier, T Daullé, Y Gorsse, A Entringer, ...
Annals of Nuclear Energy 191, 109906, 2023
12023
CFD Simulations of the Molten Salt Fast Reactor
F Martin, G Campioni, A Bergeron, Y Gorsse, E Merle, A Gerschenfeld
20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2023
12023
Molten Salt Fast Reactors: a Thermal-Hydraulics Study with RANS Models and Large Eddy Simulations
U Bieder, Y Gorsse, F Martin
Proc. Proceeding of the 9th International Conference & Workshop REMOO-2019 …, 2019
12019
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