A comparison between oxide and metallic fueled ASTRID-like reactors von Garcia-Cervantes, E-Y, Francois, J L

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COMPARISON OF THE NEUTRONIC BEHAVIOR OF A PWR TYPE SMR CORE USING CERMET AND TRISO FUEL/COMPARACION EN EL DESEMPENO NEUTRONICO DEL NUCLEO DE UN SMR DE TIPO PWR USANDO COMBUSTIBLE C... von Rosales, J, Francois, J.L, Garcia, C

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CONCEPTUAL DESIGN UPDATE OF A SMALL MODULAR REACTOR CORE USING TRISO FUEL/ACTUALIZACION EN EL DISENO CONCEPTUAL DEL NUCLEO DE UN REACTOR MODULAR PEQUEÑO USANDO COMBUSTIBLE TRISO von Garcia, C, Rosales, J, Francois, J.L, Granados, R, Martinez, H

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Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT von Lopez-Solis, R.C., François, J.L., Bastida-Ortiz, G.E., Becker, M., Sánchez-Espinoza, V.H.

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COMPARISON OF THE NEUTRONIC BEHAVIOR OF A PWR TYPE SMR CORE USING CERMET AND TRISO FUEL/COMPARACION EN EL DESEMPENO NEUTRONICO DEL NUCLEO DE UN SMR DE TIPO PWR USANDO COMBUSTIBLE C... von Rosales, J, Francois, J.L, Garcia, C

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CONCEPTUAL DESIGN UPDATE OF A SMALL MODULAR REACTOR CORE USING TRISO FUEL/ACTUALIZACION EN EL DISENO CONCEPTUAL DEL NUCLEO DE UN REACTOR MODULAR PEQUEÑO USANDO COMBUSTIBLE TRISO von Garcia, C, Rosales, J, Francois, J.L, Granados, R, Ma

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Neutrons absorbed dose rate calculations for interstitial brachytherapy with 252Cf sources von Paredes, L., Azorín, J., Balcázar, M., Francois, J.L.

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Stand-alone core sensitivity and uncertainty analysis of ALFRED from Monte Carlo simulations von Pérez-Valseca, A.-D., Espinosa-Paredes, G., François, J.L., Vázquez Rodríguez, A., Martín-del-Campo, C.

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Moving towards the global control of foot and mouth disease: an opportunity for donors: EN- -FR- Vers le contrôle mondial de la fièvre aphteuse : un objectif pour les bailleurs de... von FORMAN, S., LE GALL, F., BELTON, D., EVANS, B., FRANCOIS, J.L., MURRAY, G., SHEESLEY, D., VANDERMISSEN, A., YOSHIMURA, SH

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AXIAL: a system for boiling water reactor fuel assembly axial optimization using genetic algorithms von Martin del Campo, C, Francois, J L, Lopez, HA

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A 232Th closed fuel cycle utilizing both a thermal and hybrid nuclear systems von Perez-Gamboa, M., Nieto-Perez, M., Mahajan, S., Valanju, P., Kotschenreuther, M., François, J.L.

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Neutron kerma coefficient: Reference tissue for tumours von Paredes, L., Azorín, J., Balcázar, M., François, J.L.

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Study of the radiotoxicity of actinides recycling in boiling water reactors fuel von FRANCOIS, J. L, GUZMAN, J. R, MARTIN-DEL-CAMPO, C

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LWR spent fuel transmutation with fusion-fission hybrid reactors von François, J.L., Dorantes, J.J., Martín-del-Campo, C., Herrera, J.J.E.

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A novel method for transuranic fuel design von Guzman, J R, Espinosa-Paredes, G, Francois, J L, Martin-Del-Campo, C

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Radiotoxicity of transuranics recycling in heterogeneous fuel assemblies for boiling water reactors von GUZMAN, J. R, ESPINOSA-PAREDES, G, FRANCOIS, J. L, MARTIN-DEL-CAMPO, C, NUNEZ-CARRERA, A

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A practical optimization procedure for radial BWR fuel lattice design using tabu search with a multiobjective function von François, J.L., Martı&#x0301, n-del-Campo, C., François, R., Morales, L.B.

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BWR fuel reloads design using a Tabu search technique von Castillo, Alejandro, Alonso, Gustavo, Morales, Luis B., Martı́n del Campo, Cecilia, François, J.L., del Valle, Edmundo

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Wordplay and Metalinguistic / Metadiscursive Reflection. Authors, Contexts, Techniques, and Meta-Reflection von Winter-Froemel, Esme, Zirker, Angelika

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SOPRAG: a system for boiling water reactors reload pattern optimization using genetic algorithms von Francois, J L, Lopez, HA

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