| APOLLO2 year 2010 R Sanchez, I Zmijarevi, M Coste-Delclaux, E Masiello, S Santandrea, ... Nuclear engineering and technology 42 (5), 474-499, 2010 | 303 | 2010 |
| APOLLO3®: CEA/DEN DETERMINISTIC MULTI-PURPOSE CODE FOR REACTOR PHYSICS ANALYSIS Physor2016, 2016 | 174* | 2016 |
| Treatment of boundary conditions in trajectory-based deterministic transport methods R Sanchez, L Mao, S Santandrea Nuclear science and engineering 140 (1), 23-50, 2002 | 118 | 2002 |
| Acceleration techniques for the characteristic method in unstructured meshes S Santandrea, R Sanchez Annals of Nuclear Energy 29 (4), 323-352, 2002 | 72 | 2002 |
| Analysis and improvements of the DPN acceleration technique for the method of characteristics in unstructured meshes S Santandrea, R Sanchez Annals of Nuclear Energy 32 (2), 163-193, 2005 | 56 | 2005 |
| APOLLO3 Homogenization Techniques for Transport Core Calculations - Application to the ASTRID CFV Core SS J-F. Vidal, P. Archier, B. Faure, V. Jouault, J-M. Palau, V. Pascal, G ... M&C2017, 2017 | 42* | 2017 |
| A linear surface characteristics approximation for neutron transport in unstructured meshes S Santandrea, R Sanchez, P Mosca Nuclear science and engineering 160 (1), 23-40, 2008 | 41 | 2008 |
| Optimized tracking strategies for step MOC calculations in extruded 3D axial geometries D Sciannandrone, S Santandrea, R Sanchez Annals of Nuclear Energy 87, 49-60, 2016 | 34 | 2016 |
| A neutron transport characteristics method for 3D axially extruded geometries coupled with a fine group self-shielding environment S Santandrea, D Sciannandrone, R Sanchez, L Mao, L Graziano Nuclear Science and Engineering 186 (3), 239-276, 2017 | 33 | 2017 |
| An Integral Multidomain DPN Operator as Acceleration Tool for the Method of Characteristics in Unstructured Meshes S Santandrea Nuclear Science and Engineering 155 (2), 223-235, 2007 | 27 | 2007 |
| Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor S Santandrea, L Graziano, D Sciannandrone Annals of Nuclear Energy 113, 194-236, 2018 | 26 | 2018 |
| New Reference APOLLO3 Calculation Scheme for Sodium Cooled Fast Reactors from Sub-Assembly to Full-Core Calculations P Archier, JM Palau, JF Vidal, V Pascal, G Rimpault, B Roque, ... PHYSOR2016-Unifying Theory and Experiments in the 21st Century, 2016 | 21 | 2016 |
| High Order Method of Characteristics for 2-D Unstructured Meshes E Masiello, R Clemente, S Santandrea Proc. Int. Conf. on Mathematics, Computational Methods & Reactor Physics (M …, 2009 | 21 | 2009 |
| Positive linear and nonlinear surface characteristic schemes for the neutron transport equation in unstructured geometries S Santandrea, R Sanchez Proc. of Physor-2002, 2002 | 21 | 2002 |
| Improvements and validation of the linear surface characteristics scheme S Santandrea, JC Jaboulay, P Bellier, F Fevotte, H Golfier Annals of Nuclear Energy 36 (1), 46-59, 2009 | 20 | 2009 |
| Validation of the Newly Implemented 3D TDT-MOC Solver of APOLLO3 Code on a Whole 3D SFR Heterogeneous Assembly P Archier, JM Palau, JF Vidal, S Santandrea, D Sciannandrone PHYSOR 2016-Unifying Theory and Experiments in the 21st Century, 2016 | 19 | 2016 |
| Linear surface characteristic scheme for the neutron transport equation in unstructured geometries S Santandrea, P Mosca ANS Topical Meeting on Reactor Physics PHYSOR-2006, Vancouver, BC, Canada …, 2006 | 17 | 2006 |
| Coupled fine-group three dimensional flux calculation and subgroups method for a FBR hexagonal assembly with the APOLLO3® core physics analysis code D Sciannandrone, S Santandrea, R Sanchez, L Lei-Mao, J Vidal, J Palau, ... Mathematics and Computations, Supercomputing in Nuclear Applications and …, 2015 | 15* | 2015 |
| APOLLO3®: Overview of the new code capabilities for reactor physics analysis P Mosca, L Bourhrara, A Calloo, A Gammicchia, F Goubioud, LL Mao, ... M&C 2023, 2023 | 14 | 2023 |
| A MOC-based neutron kinetics model for noise analysis A Gammicchia, S Santandrea, I Zmijarevic, R Sanchez, Z Stankovski, ... Annals of Nuclear Energy 137, 107070, 2020 | 14 | 2020 |
François FévotteTriScale innovVerified email at triscale-innov.com
