| The breed and burn nuclear reactor: a chronological, conceptual, and technological review R Lopez‐Solis, JL François International Journal of Energy Research 42 (3), 953-965, 2018 | 29 | 2018 |
| Verification of the multi-group diffusion code AZNHEX using the OECD/NEA UAM Sodium Fast Reactor Benchmark E del-Valle-Gallegos, R Lopez-Solis, L Arriaga-Ramirez, A Gomez-Torres, ... Annals of Nuclear Energy 114, 592-602, 2018 | 14 | 2018 |
| Objectives and Status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM) International Conference on Fast Reactors and Related Fuel Cycles: Next …, 2017 | 13* | 2017 |
| Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT RC Lopez-Solis, JL François, GE Bastida-Ortiz, M Becker, ... Annals of Nuclear Energy 98, 26-35, 2016 | 13 | 2016 |
| Evaluation of the OECD/NEA/SFR-UAM neutronics reactivity feedback and uncertainty benchmarks NE Stauff, TK Kim, TA Taiwo | 11 | 2017 |
| Long-life breed/burn reactor design through reshuffle scheme R López-Solís, JL Francois-Lacouture International Journal of Nuclear Energy Science and Technology 9 (3), 263-277, 2015 | 6 | 2015 |
| Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model J Centeno-Pérez, AD Pérez-Valseca, A Gómez-Torres, RC Lopez-Solis, ... Case Studies in Thermal Engineering 30, 101694, 2022 | 3 | 2022 |
| Verification of the neutron diffusion code AZNHEX by means of the Serpent-DYN3D and Serpent-PARCS solution of the OECD/NEA SFR Benchmark A Gomez Torres, RC Lopez Solis, F Puente Espel, E Valle Gallegos, ... | 3 | 2017 |
| Verification and validation of neutronic codes using the start-up fuel load and criticality tests performed in the China Experimental Fast Reactor AM Gómez-Torres, RC Lopez-Solis, J Galicia-Aragon, X Huo, ... Proceedings of the International Conference on Fast Reactors and Related …, 2022 | 2 | 2022 |
| Comparison of KANEXT and SERPENT for fuel depletion calculations of a sodium fast reactor RC Lopez-Solis, JL Francois, M Becker, VH Sanchez-Espinoza | 2 | 2014 |
| Multiphysics and multiscale simulation for an experimental sodium-cooled fast reactor R Lopez-Solis, G Espinosa-Paredes, AD Perez-Valseca, CA Cruz-López Nuclear Engineering and Design 422, 113167, 2024 | 1 | 2024 |
| Verification and Validation of the SPL Module of the Deterministic Code AZNHEX through the Neutronics Benchmark of the CEFR Start-Up Tests G Muñoz-Peña, J Galicia-Aragon, R Lopez-Solis, A Gomez-Torres, ... Journal of Nuclear Engineering 4 (1), 59-76, 2022 | 1 | 2022 |
| Neutronics benchmark of CEFR start-up tests: reaction rates and integral reactivity coefficients TK Kim, M Jarrett, P Sciora, K Devan, SV Vedharathinam, C Batra, ... International Conference on Fast Reactors and Related Fuel Cycles …, 2022 | 1 | 2022 |
| Verification and Validation of the CEFR Serpent Model for the Generation of Reference Solutions and Cross Sections Database for The Deterministic Code AZNHEX J Galicia-Aragon, R Lopez-Solis, A Gomez-Torres, J Palacios-Hernandez, ... International Conference on Fast Reactors and Related Fuel Cycles …, 2022 | 1 | 2022 |
| Validation Exercise of the Domestic Code AZNHEX through Implementation of Macroscopic Neutron Cross-Sections Generated by SERPENT L Arriaga-Ramirez, R Lopez-Solis, A Gomez-Torres, E del-Valle-Gallegos XXX Congreso Anual de la Sociedad Nuclear Mexicana, Monterrey, Nuevo León, del 4, 2019 | 1 | 2019 |
| Solution of the OECD/NEA SFR Benchmark with the Mexican neutron diffusion code AZNHEX E Valle Gallegos, RC Lopez Solis, A Gomez Torres, F Puente Espel, ... | 1 | 2018 |
| Design of a fast breed/burn reactor core using the deterministic code KANEXT R Lopez-Solis, JL Francois Advances in Nuclear Fuel Management V (ANFM 2015) Hilton Head Island, South …, 2015 | 1 | 2015 |
| Implementation of the Breed&Burn Concept on a Sodium Fast Reactor R Lopez-Solis, JL Francois-Lacouture Proceedings of the XXX Annual Conference of the Mexican Nuclear Society, 2-5, 0 | 1 | |
| A verification exercise for the AZNHEX code using the CEFR neutronics benchmark and the OpenMC and Instant codes J Galicia Aragon, RC Lopez Solis, AM Gomez Torres, ... | | 2020 |
| Calculation of the control rod values of the experimental Chinese CEFR reactor using the Serpent code J Galicia Aragon, R Lopez Solis, A Gomez Torres, E Del Valle Gallegos, ... | | 2020 |
