| 1 | Design of a 24-month equilibrium cycle of a BWR with extended low enrichment fuel using metaheuristic optimization techniques | 2ᵒ autor: François, JL, López-Luna, J, Castillo, A, Ortiz-Servin, JJ | 2025 | ANNALS OF NUCLEAR ENERGY | WoS-id: 001386154200001
Scopus-id: 2-s2.0-85211467365
| 0 | 0 |
| 2 | Nuclear microreactors: Status review and potential applications; the Mexican case | 2ᵒ autor y autor de correspondencia: François J.-L., Morones-García E. | 2024 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 001197158700001
Scopus-id: 2-s2.0-85185533008
| 5 | 6 |
| 3 | Preface for special issue NFT-17: MX & CU & VE nuclear fission technology in Mexico, Cuba and Venezuela (+Central America) | 2ᵒ autor: François J.-L., Espinosa-Paredes G., Alonso G., Castillo A. | 2024 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 001208272100001
Scopus-id: 2-s2.0-85186073140
| 0 | 0 |
| 4 | General solution of Bateman equations using Cauchy products and the Theory of Divided Differences | Coautor y autor de correspondencia: François J.-L., Cruz-López C.-A., Espinosa-Paredes G. | 2024 | ANNALS OF NUCLEAR ENERGY | WoS-id: 001275661600001
Scopus-id: 2-s2.0-85197345967
| 2 | 2 |
| 5 | ADVANCES IN THE CONCEPTUAL DESIGN OF A SMALL MODULAR REACTOR OF THE INTEGRATED PRESSURE WATER TYPE | Coautor: François, JL, García, C, Rosales, J, Almira, S | 2024 | REVISTA CUBANA DE FISICA | WoS-id: 001285443200005
Scopus-id: 2-s2.0-85200274430
| 0 | 0 |
| 6 | Fuel loading pattern optimization of ALLEGRO fast reactor using genetic algorithms | 2ᵒ autor y autor de correspondencia: Francois, Juan-Luis, Lima-Reinaldo, Yrobel | 2023 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000860714400005
Scopus-id: 2-s2.0-85138099573
| 6 | 6 |
| 7 | A new simplified analytical solution to solve the neutron point kinetics equations using the Laplace transform method | Coautor y autor de correspondencia: Francois, Juan-Luis, Cruz-Lopez, Carlos-Antonio, Espinosa-Paredes, Gilberto | 2023 | COMPUTER PHYSICS COMMUNICATIONS | WoS-id: 000891612700001
Scopus-id: 2-s2.0-85140613545
| 6 | 6 |
| 8 | Neutronic assessment of the use of burnable absorbers for the excess reactivity control in a PWR-type SMR core with TRISO particles | 2ᵒ autor: François J.-L., Rosales J., García C. | 2023 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000947047100001
Scopus-id: 2-s2.0-85148331538
| 2 | 2 |
| 9 | Design analysis of a printed circuit heat exchanger for HTGR using a 3D finite elements model | 2ᵒ autor: François J.-L., de la Torre, Raciel, Lin C.-X. | 2023 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000967205500001
Scopus-id: 2-s2.0-85150439528
| 1 | 1 |
| 10 | Alternatives to the burnup strategy and fuel material of the EM2 modular reactor | 2ᵒ autor y autor de correspondencia: François J.-L., Morones-García E. | 2023 | ANNALS OF NUCLEAR ENERGY | WoS-id: 001016473200001
Scopus-id: 2-s2.0-85143698917
| 1 | 1 |
| 11 | Multiphysics assessment of a PWR-type SMR core using Spherical Cermet fuel through a neutronic and thermohydraulic coupled study | 2ᵒ autor: François J.-L., Rosales J., García C. | 2023 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 001103717900001
Scopus-id: 2-s2.0-85175211678
| 1 | 1 |
| 12 | Fuel loading pattern optimization of ALLEGRO fast reactor using the tabu search metaheuristic technique | Coautor: François J.-L., Lima-Reinaldo Y., Castillo A., Ortiz-Servin J.-J. | 2023 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 001149137200001
Scopus-id: 2-s2.0-85165359159
| 4 | 4 |
| 13 | Long-term planning scenarios of new nuclear capacity in Mexico using the IAEA INPRO methodology | Coautor: François J.-L., Yañez E.-J., Martin-del-Campo, Cecilia, Puente-Espel, Federico | 2022 | INTERNATIONAL JOURNAL OF ENERGY RESEARCH | WoS-id: 000649170600001
Scopus-id: 2-s2.0-85105444381
| 1 | 1 |
| 14 | Development of the General Bateman Solution using fractional calculus: A theoretical and algorithmic approach | Coautor y autor de correspondencia: François J.-L., Cruz-Lopez, Carlos-Antonio, Espinosa-Paredes, Gilberto | 2022 | COMPUTER PHYSICS COMMUNICATIONS | WoS-id: 000754669600013
Scopus-id: 2-s2.0-85121877162
| 15 | 17 |
| 15 | Neutronic and thermohydraulic analysis of a SMR-PWR core with TRISO fuel based on a 2(n) multifactorial analysis | 2ᵒ autor: François J.-L., Rosales, Jesus, Ortiz, Annie, Garcia, Carlos | 2022 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000782574000002
Scopus-id: 2-s2.0-85121722759
| 12 | 11 |
| 16 | Neutronic assessment of a PWR-type SMR core with TRISO particles using mixed-oxide fuel strategies | 2ᵒ autor: François J.-L., Rosales, Jesus, Garcia, Carlos | 2022 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000880792900004
Scopus-id: 2-s2.0-85140060796
| 4 | 4 |
| 17 | COMPARISON OF THE NEUTRONIC BEHAVIOR OF A PWR TYPE SMR CORE USING CERMET AND TRISO FUEL | 2ᵒ autor: Francois, J. L., Rosales, J., Garcia, C. | 2022 | REVISTA CUBANA DE FISICA | WoS-id: 000902017500003
Scopus-id: 2-s2.0-85152410777
| 1 | 1 |
| 18 | CONCEPTUAL DESIGN UPDATE OF A SMALL MODULAR REACTOR CORE USING TRISO FUEL | Coautor: Francois, J. L., Garcia, C., Rosalles, J., Granados, R., et al. | 2022 | REVISTA CUBANA DE FISICA | WoS-id: 000902017500004
Scopus-id: 2-s2.0-85160933640
| 2 | 2 |
| 19 | Optimization and heat transfer correlations development of zigzag channel printed circuit heat exchangers with helium fluids at high temperature | 2ᵒ autor: Francois, Juan-Luis, de la Torre, Raciel, Lin, Cheng-Xian | 2021 | INTERNATIONAL JOURNAL OF THERMAL SCIENCES | WoS-id: 000599626000005
Scopus-id: 2-s2.0-85092311973
| 35 | 38 |
| 20 | Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor | Coautor y autor de correspondencia: Francois, J. L., Juarez, L. C., Torres, I, J. | 2021 | Journal of Nuclear Engineering and Radiation Science | WoS-id: 000658359300011
Scopus-id: 2-s2.0-85127871886
| 0 | 2 |
| 21 | Neutronic analysis of the NuScale core using accident tolerant fuels with different coating materials | 2ᵒ autor y autor de correspondencia: François J.-L., Pino-Medina, Sadiel | 2021 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000663078800005
Scopus-id: 2-s2.0-85102967720
| 18 | 22 |
| 22 | Neutronic analysis of the ALLEGRO fast reactor core with deterministic ERANOS code and Monte Carlo Serpent code | 2ᵒ autor y autor de correspondencia: Francois Lacouture, Juan Luis, Lima Reinaldo, Yrobel | 2021 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000690404700003
Scopus-id: 2-s2.0-85110766112
| 10 | 9 |
| 23 | Editorial: A preface to the special issue on ?PHYSOR-2018: Reactor Physics Paving the Way Towards More Efficient Systems, 22?26 April 2018, Cancun, Mexico? | 1ᵉʳ autor: François J.-L., Alonso, Gustavo, Valle E.D., Maldonado, G. Ivan | 2020 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000496898500058
Scopus-id: 2-s2.0-85071172460
| 0 | 0 |
| 24 | A hybrid system for optimizing enrichment and gadolinia distributions in BWR fuel lattices | Coautor: François J.-L., Montes-Tadeo J.-L., Perusquia-del-Cueto, Raul, Pelta, David A., et al. | 2020 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000508745700019
Scopus-id: 2-s2.0-85073058755
| 0 | 0 |
| 25 | Coupled Monte Carlo-CFD analysis of heat transfer phenomena in a supercritical water reactor fuel assembly | 2ᵒ autor: François J.-L., Castro, Landy, Garcia, Carlos | 2020 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000526111300021
Scopus-id: 2-s2.0-85077942403
| 12 | 14 |
| 26 | Time-space fractional neutron point kinetics: Theory and simulations | 2ᵒ autor: François J.-L., Espinosa-Martínez E.-G., Martin-del-Campo C., Maleki Moghaddam N. | 2020 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000530684200015
Scopus-id: 2-s2.0-85081654364
| 11 | 11 |
| 27 | Coupled Monte Carlo-burnup and CFD analysis of coated UN and UC fuels in an HPLWR fuel assembly | 2ᵒ autor: François J.-L., Castro L., García C. | 2020 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000534352400017
Scopus-id: 2-s2.0-85082515666
| 4 | 4 |
| 28 | Two alternative approaches to the solution of cyclic chains in transmutation and decay problems | 2ᵒ autor y autor de correspondencia: Luis Francois, Juan, Cruz Lopez, Carlos Antonio | 2020 | COMPUTER PHYSICS COMMUNICATIONS | WoS-id: 000541251200005
Scopus-id: 2-s2.0-85081264885
| 4 | 4 |
| 29 | Assessment of the design effects on the structural performance of the Printed Circuit Heat Exchanger under very high temperature condition | 2ᵒ autor: Francois, Juan-Luis, de la Torre, Raciel, Lin, Cheng-Xian | 2020 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000550672100006
Scopus-id: 2-s2.0-85086401651
| 17 | 17 |
| 30 | Analysis of the use of thorium in the GFR2400 gas-cooled fast reactor | 2ᵒ autor: François J.-L., Lima-Reinaldo, Yrobel, Martin-del-Campo, Cecilia | 2019 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000456923500002
Scopus-id: 2-s2.0-85059189734
| 11 | 12 |
| 31 | Study of the homogeneous and heterogeneous Am transmutation in an ELFR-like reactor loaded with nitride fuel | 2ᵒ autor y autor de correspondencia: François J.-L., Juárez L.-C. | 2019 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000463120200003
Scopus-id: 2-s2.0-85057824821
| 4 | 4 |
| 32 | Comparative study of the neutronic performance of thorium-based metallic fuel and MOX fuel in an ASTRID-like fast reactor core | 2ᵒ autor: François J.-L., Escorcia-Ortiz D., Martín-del-Campo C. | 2019 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000465217900012
Scopus-id: 2-s2.0-85063688017
| 3 | 3 |
| 33 | Life cycle assessment of a combined-cycle gas turbine with a focus on the chemicals used in water conditioning | Coautor: François J.-L., Toscano C.F., Martin-del-Campo C., Moeller-Chavez G., et al. | 2019 | SUSTAINABILITY | WoS-id: 000471010300195
Scopus-id: 2-s2.0-85067108010
| 16 | 20 |
| 34 | A preliminary comparative study between oxide and metallic fuelled ASTRID-like reactor under a B&B strategy | 1ᵉʳ autor: François J.-L., García-Cervantes E.-Y., Martín-Del-Campo C. | 2019 | International Journal of Nuclear Energy Science and Technology | Scopus-id: 2-s2.0-85066026406
| 0 | 0 |
| 35 | The breed and burn nuclear reactor: A chronological, conceptual, and technological review | 2ᵒ autor y autor de correspondencia: François J.-L., Lopez-Solis R. | 2018 | INTERNATIONAL JOURNAL OF ENERGY RESEARCH | WoS-id: 000425185500006
Scopus-id: 2-s2.0-85042110895
| 18 | 22 |
| 36 | Comparative neutronic study of homogeneous and heterogeneous thorium fuel based core design in a lead-cooled fast reactor | 2ᵒ autor y autor de correspondencia: François J.-L., Juárez-Martínez L.-C. | 2018 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000427338000011
Scopus-id: 2-s2.0-85037977031
| 6 | 6 |
| 37 | An alternative algorithm for the linearization process of transmutation and decay networks | 2ᵒ autor y autor de correspondencia: Francois, Juan-Luis, Cruz-Lopez, Carlos-Antonio | 2018 | COMPUTER PHYSICS COMMUNICATIONS | WoS-id: 000437964200010
Scopus-id: 2-s2.0-85047415686
| 4 | 4 |
| 38 | Initial verification of AZNHEX hexagonal-z neutron diffusion code with MCNP6 for two different study cases | 2ᵒ autor: François J.-L., Galicia-Aragón J., Bastida-Ortiz G.E., Martín-del-Campo C., et al. | 2018 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000442314600027
Scopus-id: 2-s2.0-85044789849
| 1 | 1 |
| 39 | Neutronic study of an ASTRID-like fast reactor core with thorium-based fuel | 2ᵒ autor y autor de correspondencia: François J.-L., Escorcia-Ortiz D. | 2018 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000446333700015
Scopus-id: 2-s2.0-85053482436
| 4 | 5 |
| 40 | Stand-alone core sensitivity and uncertainty analysis of ALFRED from Monte Carlo simulations | Coautor: Francois, J. L., Perez-Valseca, A. -D., Espinosa-Paredes, G., Vazquez Rodriguez, A., et al. | 2017 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000403625200010
Scopus-id: 2-s2.0-85018754632
| 6 | 7 |
| 41 | On the stability of fractional neutron point kinetics (FNPK) | Coautor: Francois, Juan-Luis, Espinosa-Paredes, Gilberto, Cazares-Ramirez, Ricardo-I., Martin-del-Campo, Cecilia | 2017 | APPLIED MATHEMATICAL MODELLING | WoS-id: 000405445300033
Scopus-id: 2-s2.0-85018750964
| 14 | 15 |
| 42 | Study on the temperature distributions in fuel assemblies of lead-cooled fast reactors | 2ᵒ autor: François, J.-L., Espinosa-Paredes G., Sánchez-Mora H., Pérez-Valseca A.D., et al. | 2017 | International Journal of Nuclear Energy Science and Technology | Scopus-id: 2-s2.0-85027417478
| 0 | 7 |
| 43 | Verification of AZTRAN vl.2 code with a PWR-MOX benchmark problem | Coautor: François J.-L., Vallejo-Quintero J.-A., Bastida-Ortiz G.-E., Xolocostli-Munguía J.-V., et al. | 2017 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-85033439874
| 0 | 2 |
| 44 | AZTRAN and AZKIND verification with a BWR study case | Coautor: François J.-L., Bastida-Ortiz G.-E., Vallejo-Quintero J.-A., Galicia-Aragon J., et al. | 2017 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-85033455431
| 0 | 1 |
| 45 | Fast reactor core analysis using AZNHEX neutron diffusion code | 2ᵒ autor: François, J.-L., Galicia-Aragón J., Bastida-Ortiz, G.-E., Del-Valle-Gallegos E., et al. | 2017 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-85033476931
| 0 | 0 |
| 46 | Study on the use of thorium in a lead-cooled fast reactor | 2ᵒ autor y autor de correspondencia: François J.-L., Juárez-Martínez L.-C. | 2017 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-85062039956
| 0 | 2 |
| 47 | Estimation of the fast neutron fluence in Laguna Verde RPV-Steel specimens simulating their irradiation in a TRIGA reactor | 2ᵒ autor: Luis Francois-Lacouture, Juan, Galicia-Aragon, Juan, Aguilar-Hernandez, Fortunato | 2016 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000372564400028
Scopus-id: 2-s2.0-84955602453
| 4 | 4 |
| 48 | A comparison between oxide and metallic fueled ASTRID-like reactors | 2ᵒ autor y autor de correspondencia: Francois, J. L., Garcia-Cervantes, E. -Y. | 2016 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000377231600039
Scopus-id: 2-s2.0-84963623674
| 3 | 4 |
| 49 | Minimal global regret analysis for electricity generation expansion | 2ᵒ autor: Luis Francois, Juan, Martin-del-Campo, Cecilia, Jose Estrada, Guillermo | 2016 | ENERGY SOURCES PART B-ECONOMICS PLANNING AND POLICY | WoS-id: 000378707800011
Scopus-id: 2-s2.0-84975290487
| 3 | 5 |
| 50 | Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT | 2ᵒ autor: Francois, J. L., Lopez-Solis, R. C., Bastida-Ortiz, G. E., Becker, M., et al. | 2016 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000383820400004
Scopus-id: 2-s2.0-84979518421
| 4 | 4 |
| 51 | Effect of heat transfer correlations on the fuel temperature prediction of SCWRs | Coautor: Francois, Juan-Luis, Espinosa-Martinez, Erick-Gilberto, Martin-del-Campo, Cecilia, Espinosa-Paredes, Gilberto | 2016 | Epj Nuclear Sciences & Technologies | WoS-id: 000384806100002
| 0 | 0 |
| 52 | Life cycle assessment of hydrogen production from a high temperature electrolysis process coupled to a high temperature gas nuclear reactor | 2ᵒ autor: Francois, JL, Giraldi, MR, MartindelCampo, C | 2015 | INTERNATIONAL JOURNAL OF HYDROGEN ENERGY | WoS-id: 000350939900023
Scopus-id: 2-s2.0-84923313336
| 45 | 51 |
| 53 | A 232Th closed fuel cycle utilizing both a thermal and hybrid nuclear systems | Coautor: Francois, JL, Perez-Gamboa M., Nieto-Perez M., Mahajan S., et al. | 2015 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000358468300014
Scopus-id: 2-s2.0-84926383321
| 1 | 1 |
| 54 | Searching for enrichment and gadolinia distributions in BWR fuel lattices through a Heuristic-Knowledge Method | Coautor: Francois, JL, MontesTadeo, JL, Perusquía-Del-Cueto R., Martín-Del-Campo C., et al. | 2015 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000363349100019
Scopus-id: 2-s2.0-84933499765
| 2 | 2 |
| 55 | Long-life breed/burn reactor design through reshuffle scheme | 2ᵒ autor y autor de correspondencia: Francois-Lacouture J.L., López-Solís R. | 2015 | International Journal of Nuclear Energy Science and Technology | Scopus-id: 2-s2.0-84954433926
| 0 | 2 |
| 56 | Comparison of heuristic optimization techniques for the enrichment and gadolinia distribution in BWR fuel lattices and decision analysis | Coautor: Francois, JL, Castillo A., Martín-Del-Campo C., Montes-Tadeo, JL, et al. | 2014 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000327829400062
Scopus-id: 2-s2.0-84884626306
| 6 | 9 |
| 57 | PSA applied to the design of non-nuclear plants | Coautor: Francois J.L., Ruiz-Sánchez T., Nelson P.F., Cruz-Gómez M.J. | 2014 | Safety, Reliability And Risk Analysis: Beyond The Horizon - Proceedings Of The European Safety And Reliability Co | Scopus-id: 2-s2.0-84900007899
| 0 | 0 |
| 58 | MCNPX and HELIOS-2 comparison for the neutronics calculations of a Supercritical Water Reactor HPLWR | Coautor: Francois, JL, Barragan-Martinez, AM, Martin-del-Campo, C, Espinosa-Paredes, G | 2013 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000311660700021
Scopus-id: 2-s2.0-84867074306
| 7 | 8 |
| 59 | Comparison of metaheuristic optimization techniques for BWR fuel reloads pattern design | 1ᵉʳ autor: Francois, JL, Ortiz-Servin J.J., Martín-Del-Campo C., Castillo A., et al. | 2013 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000311660700022
Scopus-id: 2-s2.0-84867054028
| 18 | 19 |
| 60 | Neutronic design of a very high temperature reactor core with low graphite content | 2ᵒ autor: Francois, JL, Telesforo-Reyes, D, Martin-del-Campo, C, Reinking-Cejudo, AG | 2013 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000317157800010
Scopus-id: 2-s2.0-84872697372
| 4 | 4 |
| 61 | LWR spent fuel transmutation with fusion-fission hybrid reactors | 1ᵉʳ autor: Francois, JL, Dorantes, JJ, Martin-del-Campo, C, Herrera, JJE | 2013 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000318465700006
Scopus-id: 2-s2.0-84874818179
| 5 | 4 |
| 62 | Validation of simplified methods for fuel depletion calculations in gas-cooled fast reactors | Coautor y autor de correspondencia: Francois, JL, Martin-del-Campo, C, Reyes-Ramirez, R | 2013 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000322854700027
Scopus-id: 2-s2.0-84878784439
| 3 | 5 |
| 63 | Transient analysis in a supercritical water reactor concept with multiple heat-up steps | Coautor: François J.L., Barragán-Martínez A.M., Espinosa-Paredes G., Vázquez-Rodríguez A., et al. | 2013 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-84902800748
| 0 | 0 |
| 64 | Application of the accident consequence analysis in the emergency system design of an SI cycle hydrogen production plant | Coautor: Francois, JL, Ruiz-Sanchez, T, Nelson, PF, Cruz-Gomez, MJ, et al. | 2012 | INTERNATIONAL JOURNAL OF HYDROGEN ENERGY | WoS-id: 000303952300069
Scopus-id: 2-s2.0-84859209494
| 9 | 11 |
| 65 | Life cycle greenhouse gases emission analysis of hydrogen production from S-I thermochemical process coupled to a high temperature nuclear reactor | 2ᵒ autor: Francois, JL, Giraldi, MR, Castro-Uriegas, D | 2012 | INTERNATIONAL JOURNAL OF HYDROGEN ENERGY | WoS-id: 000309493600004
Scopus-id: 2-s2.0-84866108245
| 31 | 34 |
| 66 | Fuel lattice design in a boiling water reactor using an ant-colony-based system | 2ᵒ autor: Francois, JL, Montes J.L., Ortiz J.J., Martín-Del-Campo C., et al. | 2011 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000290194100013
Scopus-id: 2-s2.0-79953761980
| 14 | 17 |
| 67 | Contributions to the neutronic analysis of a gas-cooled fast reactor | Coautor: Francois, JL, Martin-del-Campo, C, Reyes-Ramirez, R, Reinking-Cejudo, AG | 2011 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000290194100022
Scopus-id: 2-s2.0-79953737881
| 6 | 11 |
| 68 | Design and optimization of an equilibrium reload with MOX fuel with minor actinides | 1ᵉʳ autor: Francois, JL, Guzman, JR, Martin-del-Campo, C, Palomera, MA | 2011 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000294319400004
Scopus-id: 2-s2.0-79960557576
| 10 | 11 |
| 69 | Neutron absorbed dose rate with Cf-252 sources for medical applications | Coautor: Francois, JL, Paredes, L, Azorin, J, Balcazar, M | 2010 | REVISTA MEXICANA DE FISICA | WoS-id: 000275031400011
| 2 | 0 |
| 70 | Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a Gas-cooled Fast Reactor | Coautor: Francois, JL, Reyes-Ramirez, R, Martin-del-Campo, C, Brun, E, et al. | 2010 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000279277300008
Scopus-id: 2-s2.0-78751607154
| 10 | 17 |
| 71 | Use of PSA for design of emergency systems in a sulfur-iodine cycle | Coautor y autor de correspondencia: Francois, JL, Nelson, PF, Mendoza, A | 2010 | INTERNATIONAL JOURNAL OF HYDROGEN ENERGY | WoS-id: 000279414900007
Scopus-id: 2-s2.0-77955124581
| 3 | 3 |
| 72 | A novel method for transuranic fuel design | Coautor: Francois, JL, Guzmán J.R., Espinosa-Paredes G., Martín-del-Campo C. | 2010 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000279441400013
Scopus-id: 2-s2.0-77953136753
| 4 | 4 |
| 73 | Radiotoxicity of transuranics recycling in heterogeneous fuel assemblies for boiling water reactors | Coautor: Francois, JL, Guzmán J.R., Espinosa-Paredes G., Martín-del-Campo C., et al. | 2010 | PROGRESS IN NUCLEAR ENERGY | WoS-id: 000279441400014
Scopus-id: 2-s2.0-77953233557
| 4 | 5 |
| 74 | Neutron kerma coefficient: Reference tissue for tumours | Coautor: Francois, JL, Paredes L., Azorín J., Balcázar M. | 2010 | RADIATION MEASUREMENTS | WoS-id: 000286349000087
Scopus-id: 2-s2.0-78649791142
| 3 | 3 |
| 75 | Efficiency improvement in the sulfur-iodine hydrogen production process through thermal integration | 2ᵒ autor: François J.-L., Mendoza A., Nelson P.F. | 2010 | 2nd International Topical Meeting On Safety And Technology Of Nuclear Hydrogen Production, Control, And Managemen | Scopus-id: 2-s2.0-78649381123
| 0 | 0 |
| 76 | Local power peaking factor estimation in nuclear fuel by artificial neural networks | 2ᵒ autor: Francois, JL, Montes J.L., Ortiz J.J., Martín-del-Campo C., et al. | 2009 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000263187500013
Scopus-id: 2-s2.0-58149123448
| 23 | 28 |
| 77 | Study of the radiotoxicity of actinides recycling in boiling water reactors fuel | 1ᵉʳ autor: Francois, JL, Guzmán J.R., Martín-del-Campo C. | 2009 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000270411500021
Scopus-id: 2-s2.0-68349127371
| 9 | 8 |
| 78 | Advanced and flexible genetic algorithms for BWR fuel loading pattern optimization | Coautor y autor de correspondencia: Francois, JL, Martin-del-Campo, C, Palomera-Perez, MA | 2009 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000271343600011
Scopus-id: 2-s2.0-70349253908
| 23 | 29 |
| 79 | BWR MOX fuel design with plutonium and minor actinides | 1ᵉʳ autor: François J.L., Guzmán J.R. | 2009 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-72749116494
| 0 | 0 |
| 80 | Feasibility study of boiling water reactor core based on thorium-uranium fuel concept | 2ᵒ autor: Lacouture, JLF, Nunez-Carrera, A, del Campo C.M., Espinosa-Paredes G. | 2008 | ENERGY CONVERSION AND MANAGEMENT | WoS-id: 000251625300005
Scopus-id: 2-s2.0-36049042220
| 10 | 14 |
| 81 | Transient and stability analysis of a BWR core with thorium-uranium fuel | Coautor y autor de correspondencia: Francois, JL, Nunez-Carrera, A, Espinosa-Paredes G. | 2008 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000258047700018
Scopus-id: 2-s2.0-45449092109
| 3 | 4 |
| 82 | Design of a BWR fuel with plutonium and minor actinides using tabu search | 1ᵉʳ autor: François J.L., Guzmán R., Del Campo C.M. | 2008 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-55249099085
| 0 | 0 |
| 83 | Analytical hierarchy process for the selection of nuclear reactors for Mexico | Coautor y autor de correspondencia: François J.L., Martin-Del-Campo C., Nelson P.F. | 2008 | International Conference On Advances In Nuclear Power Plants, Icapp 2008 | Scopus-id: 2-s2.0-70349862241
| 0 | 0 |
| 84 | A design-phase PSA of a nuclear-powered hydrogen plant | Coautor y autor de correspondencia: François J.L., Nelson P.F., Flores A. | 2007 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000244007500001
Scopus-id: 2-s2.0-33846116293
| 15 | 23 |
| 85 | Boiling water reactor fuel lattice enrichment distribution optimization using tabu search and fuzzy logic | 2ᵒ autor: François J.L., Martin-Del-Campo C., Barragan A.M., Palomera M.A. | 2007 | NUCL TECHNOL | WoS-id: 000244428500003
Scopus-id: 2-s2.0-33947518466
| 8 | 11 |
| 86 | Comparison between HELIOS calculations and a PWR cell benchmark for actinides transmutation | 2ᵒ autor y autor de correspondencia: François J.-L., Guzmán R. | 2007 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000245029800003
Scopus-id: 2-s2.0-33846897140
| 4 | 8 |
| 87 | Optimization of BWR fuel lattice enrichment and gadolinia distribution using genetic algorithms and knowledge | 2ᵒ autor: François J.L., Martin-del-Campo C., Carmona R., Oropeza I.P. | 2007 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000246715800002
Scopus-id: 2-s2.0-34147104438
| 16 | 25 |
| 88 | Neutrons absorbed dose rate calculations for interstitial brachytherapy with 252Cf sources | Coautor: Francois J.L., Paredes L., Azorín J., Balcázar M. | 2007 | NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | WoS-id: 000249741300149
Scopus-id: 2-s2.0-34548297599
| 7 | 7 |
| 89 | Development of a scatter search optimization algorithm for boiling water reactor fuel lattice design | 1ᵉʳ autor: François J.-L., Martín-del-Campo C., Morales L.B., Palomera M.-A. | 2007 | NUCL SCI ENG | Scopus-id: 2-s2.0-33947179488
| 0 | 11 |
| 90 | BWR fuel design using minor actinides as burnable absorber | 1ᵉʳ autor: François J.L., Guzmán R. | 2007 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-55849119579
| 0 | 1 |
| 91 | Design of a boiling water reactor core based on an integrated blanket-seed thorium-uranium concept | 2ᵒ autor: François J.L., Núñez-Carrera A., Martín-Del-Campo C., Espinosa-Paredes G. | 2005 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000227968600002
Scopus-id: 2-s2.0-13844306812
| 7 | 8 |
| 92 | BWR fuel lattice optimization using scatter search | 1ᵉʳ autor: François J.L., Martín-Del-Campo C., Morales L.B., Palomera M.A. | 2005 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-33244496671
| 0 | 0 |
| 93 | Innovative use of fuzzy logic to build objective functions in nuclear fuel optimization problems | 2ᵒ autor: François J.L., Martín-Del-Campo C., Palomera M.A., Barragán A. | 2005 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-33244497362
| 0 | 0 |
| 94 | A simplified probabilistic safety assessment of a steam-methane reforming hydrogen production plant coupled to a high-temperature gas cooled nuclear reactor | Coautor y autor de correspondencia: Francois J.L., Nelson P.F., Flores A. | 2005 | American Nuclear Society International Topical Meeting On Probabilistic Safety Analysis, Psa 05 | Scopus-id: 2-s2.0-33745832270
| 0 | 0 |
| 95 | BWR fuel reloads design using a Tabu search technique | Coautor: François J.L., Castillo A., Alonso G., Morales L.B., et al. | 2004 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000186662100003
Scopus-id: 2-s2.0-0141707684
| 28 | 37 |
| 96 | Development of a BWR control rod pattern design system based on fuzzy logic and knowledge | 1ᵉʳ autor: François J.-L., Martín-del-Campo C., Tavares A. | 2004 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000187917000001
Scopus-id: 2-s2.0-0242405916
| 8 | 10 |
| 97 | Comparison between HELIOS critical-depletion calculations and a PWR thorium cell burnup benchmark | 2ᵒ autor: François J.L., Núñez-Carrera A., Espinosa-Paredes G. | 2004 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000220203800001
Scopus-id: 2-s2.0-0347128560
| 7 | 8 |
| 98 | Development of a BWR loading pattern design system based on modified genetic algorithms and knowledge | 2ᵒ autor: François J.L., Martín-Del-Campo C., Avendaño L., González M. | 2004 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000224257800005
Scopus-id: 2-s2.0-4344669920
| 11 | 18 |
| 99 | Comparative assessment of different nuclear options and strategies for electricity generation in México using DECADES | Coautor y autor de correspondencia: Francois J.L., Del Campo C.M., Ortega R. | 2004 | Abstracts Of The Pacific Basin Nuclear Conference | Scopus-id: 2-s2.0-13244265530
| 0 | 0 |
| 100 | Development of a methodology for nuclear fuel cycle cost analysis | 1ᵉʳ autor: François J.L., Ortega R.F., Del Campo C.M., Hernández H., et al. | 2004 | Abstracts Of The Pacific Basin Nuclear Conference | Scopus-id: 2-s2.0-13244274974
| 0 | 0 |
| 101 | Model for transient and stability analysis of a BWR core with Thorium-Uranium fuel | Coautor y autor de correspondencia: François J.L., Núñez-Carrera A., Espinosa-Paredes G. | 2004 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-4344688628
| 0 | 1 |
| 102 | A practical optimization procedure for radial BWR fuel lattice design using tabu search with a multiobjective function | 1ᵉʳ autor: François J.L., Martín-del-Campo C., François R., Morales L.B. | 2003 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000183643200001
Scopus-id: 2-s2.0-0038217082
| 30 | 41 |
| 103 | Integrated methodology for BWR axial fuel assembly and reload core optimization based on genetic algorithms | 2ᵒ autor: François J.L., Martín-del-Campo C., González J. | 2003 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-0037701729
| 0 | 0 |
| 104 | Spent fuel simulation of Garigliano's light water reactor assemblies with HELIOS and ORIGEN | 1ᵉʳ autor: Francois J.L., Cortes A. | 2003 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-0038715927
| 0 | 0 |
| 105 | BWR Fuel Lattice Design Evaluation in an Operating Cycle | 2ᵒ autor: François J.L., Martín-del-Campo C., Gonzáles J. | 2003 | Transactions of the American Nuclear Society | Scopus-id: 2-s2.0-84855639589
| 0 | 0 |
| 106 | Design of an overmoderated fuel and a full MOX core for plutonium consumption in boiling water reactors | 1ᵉʳ autor: François J.L., Campo C.M.D., Hernández J. | 2002 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000176476200005
Scopus-id: 2-s2.0-0036832933
| 6 | 6 |
| 107 | Boiling water reactor fuel assembly axial design optimization using tabu search | 2ᵒ autor: François J.L., Martín-del-Campo C., Morales L.B. | 2002 | NUCL SCI ENG | Scopus-id: 2-s2.0-0036743810
| 0 | 16 |
| 108 | AXIAL: A system for boiling water reactor fuel assembly axial optimization using genetic algorithms | 2ᵒ autor: François J.L., Martín Del Campo C., López H.A. | 2001 | ANNALS OF NUCLEAR ENERGY | Scopus-id: 2-s2.0-0035501891
| 0 | 31 |
| 109 | Validation of a methodology for fuel management analysis of Laguna Verde nuclear power plant | 1ᵉʳ autor: François J.L., Esquivel J.L., Cortés C., Esquivias J., et al. | 2001 | ANNALS OF NUCLEAR ENERGY | Scopus-id: 2-s2.0-0343338376
| 4 | 4 |
| 110 | SOPRAG: A system for boiling water reactors reload pattern optimization using genetic algorithms | 1ᵉʳ autor: François J.L., López H.A. | 1999 | ANNALS OF NUCLEAR ENERGY | WoS-id: 000079590100002
Scopus-id: 2-s2.0-0033177439
| 22 | 31 |
| 111 | Development of an automated system for fuel reload patterns design | 1ᵉʳ autor: François J.L., Martín Del Campo C., Cortés C.C., Ramírez E., et al. | 1999 | NUCLEAR ENGINEERING AND DESIGN | WoS-id: 000083714000002
Scopus-id: 2-s2.0-0342732917
| 5 | 6 |
ID's SCOPUS 