Portal de Transparencia

Actividad investigadora:

• Artículos en revistas
  • [2019] Nuclear data analyses for improving the safety of advanced lead-cooled reactors
  • [2018] Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators
  • [2018] Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
  • [2018] Stress-testing the ALFRED design - Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients
  • [2017] Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
  • [2017] Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
  • [2017] Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
  • [2017] Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
  • [2017] Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
  • [2017] Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
  • [2017] Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
  • [2017] Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
  • [2017] Testing the NURESIM platform on a PWR main steam line break benchmark
  • [2017] Testing the NURESIM platform on a PWR main steam line break benchmark
  • [2016] Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference
  • [2016] Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference
  • [2014] Educating Nuclear Engineers by Nuclear Science and TEchnology Master at UPM
  • [2014] Effects of cross sections tables generation and optimization on rod ejection transient analyses
  • [2014] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
  • [2014] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
  • [2014] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
  • [2013] A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
  • [2013] A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
  • [2013] A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
  • [2013] A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
  • [2012] Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR
  • [2011] Desarrollo de códigos neutrónicos propios para la simulación del núcleo de reactores PWR
  • [2011] Education and training of future nuclear engineers throught the use of an interactive plant simulator
  • [2011] Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
  • [2011] Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
  • [2011] Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
  • [2010] Assessment of fissionable material behaviour in fission chambers
  • [2010] Assessment of fissionable material behaviour in fission chambers
  • [2010] Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
  • [2010] Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
  • [2010] Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
  • [2010] Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
  • [2010] Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
  • [2009] Effect of activation cross section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2009] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2009] Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
  • [2008] Participación española en el desarrollo de la Plataforma Europea para Simulación de Reactores Nucleares (NURESIM)
  • [2008] Propagation of Statistical and Nuclear Data Uncertainties in Monte-Carlo Burn-up Calculations
  • [2008] The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis
  • [2007] Applications of Monte Carlo techniques for propagation of cross section uncertainties to actinide inventory in ADS transmuters: comparison with sensitivity analysis
  • [2007] The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations
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• Capítulos de libros
  • [2016] Results of UPM and CSN for the Burn-up Credit Criticality Safety Benchmark Phase III-C
  • [2007] Development and Performance of the Analytic Nodal Diffusion Solver ANDES in Multigroups for 3D Rectangular Geometry
• Conferencias invitadas en congresos
  • [2017] Overview of the UPM-CSN activities for Uncertainty Quantification in PWR full core simulations
  • [2017] Overview of the UPM-CSN activities for Uncertainty Quantification in PWR full core simulations
  • [2016] Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor
  • [2009] IAEA Technical Meeting in colaboration with NEA on Specific Applications of Research Reactor: Provision of Nuclear Data.
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• Cursos, seminarios y tutoriales
  • [2018] ESFR-SMART Workshop on Liquid Metal Facilities: Nuclear data Sensitivity/Uncertainty Analysis in Nuclear Applications
  • [2016] GENTLE Intersemester Course on Nuclear Data Processing and Use in Nuclear Applications
• Informes para las AAPP o sus organismos dependientes
  • [2008] ”Final Report and sample test problems for use of the core scope COBAYA3 / ANDES code in steady-state/eigenvalue and transient/source problems of multi-group diffusion for 3D rectangular and hexagonal-triangular geometries integrated in the common NURESIM platform”
  • [2008] ”Report and sample/test problems for use of the advanced core- lattice methods integrated into the NURESIM common package by linking via SALOME”
• Otras Publicaciones
  • [2019] Benchmarking KENO-VI against MCNP/Serpent using a simplified SFR pin-cell problem
  • [2019] D1.2.1. Initial core performance and burnup calculations
  • [2019] OECD/NEA WPEC SG 46: ''Joint CIEMAT and UPM contribution: ASTRID, ALFRED and MYRRHA''
  • [2019] OECD/NEA WPEC SG 46: ''Status on MYRRHA, ESFR, ASTRID and ALFRED''
  • [2019] Status on MYRRHA, ESFR, ASTRID and ALFRED
  • [2012] Definition and development of the automated pre- and post-processing procedures and codes to generate advanced cell and nodal XS libraries for PWR, BWR and VVER, covering the full parameter space of operation, burn-up and transient conditions
  • [2012] Definition and tools for Advanced Cell and Nodal Cross Section Libraries and Definition of the interface between APOLLO2 and DYN3D and COBAYA3
  • [2011] Report on the results of PWR benchmarks using COBAYA3 and DYN3D pin-by-pin
  • [2008] ”Integration of ANDES and COBAYA in SALOME”
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• Otros méritos
  • [2019] Miembro del comité de expertos de la campaña 2018-2019 del Hcéres (Haut Conseil de l'évaluation de la recherche et de l'enseignement supérieur)
  • [2018] Miembro del comité de expertos de la campaña 2018-2019 del Hcéres (Haut Conseil de l'évaluation de la recherche et de l'enseignement supérieur)
  • [2018] Revisión de artículo en revista NUCLEAR TECHNOLOGY
• Ponencia en Congresos
  • [2019] About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors
  • [2019] About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors
  • [2019] Active learning in reactor physics using state-of-the-art simulation tools at Universidad Politécnica de Madrid
  • [2019] Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months
  • [2019] Identificación y modelización de experimentos de criticidad en apoyo a la validación del código de transporte neutrónico de Monte Carlo KENO-VI/SCALE y bases de datos asociadas
  • [2019] Nuclear data assimilation for MYRRHA
  • [2018] Conceptual design of the ESFR reactor core catcher in the ESFR-SMART project
  • [2018] Methodologies for Sensitivity/Uncertainty Analysis Using Reactor Core Simulators with Application to Pressurized Water Reactors
  • [2018] Nuclear data analyses for improving the safety of advanced lead-cooled reactors
  • [2018] Nuclear data analyses for improving the safety of advanced lead-cooled reactors
  • [2018] Sensitivity and Uncertainty Methods for Effective Delayed Neutron Fraction and Neutron Generation Time With Summon
  • [2018] Spanish contribution to the Superphénix reactor benchmark for neutronics validation
  • [2018] Spanish contribution to the Superphénix reactor benchmark for neutronics validation
  • [2017] Análisis de las incertidumbres en los factores de pico de un núcleo PWR
  • [2017] Análisis de las incertidumbres en los factores de pico de un núcleo PWR
  • [2017] Coupled calculations COBAYA4/CTF for different MSLB scenarios in the frame of NURESAFE project
  • [2017] Impact of nuclear data uncertainties on the reactivity coefficients of ALFRED
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Nuclear Data sensitivity and uncertainty assessment of the sodium voiding reactivity coefficients pf an ASTRID-like sodium fast reactor
  • [2017] Results for Exercise I-3 with COBAYA: Analysis of the peaking power factors
  • [2017] Validation of COBAYA4/CTF coupling within European NURESIM Platform against MCNP/CTF
  • [2016] : Coolant materials description in the new JEFF-3.3T1 for GEN-IV reactors
  • [2016] Coolant materials description in the new JEFF-3.3T1 for GEN-IV reactors
  • [2016] Coolant materials description in the new JEFF-3.3T1 for GEN-IV reactors
  • [2016] Exercise I-3: Comparison of uncertainty propagation in nodal and pin-by-pin calculations using COBAYA code
  • [2016] Impact of fuel modeling and TH uncertainties in a MSLB scenario
  • [2016] Nuclear Data Uncertainties for typical fuel assemblies and a simple reactor core
  • [2016] Nuclear data sensitivity analysis and evaluated data library comparison for MYRRHA relevant quantities
  • [2016] Nuclear data sensitivity analysis and evaluated data library comparison for MYRRHA relevant quantities
  • [2016] Preparing uncertainty quantification in multi-physics and multi-scale core simulations using COBAYA and CTF codes
  • [2016] Sensitivity and Uncertainty analysis of MYRRHA lead-bismuth cooled fast reactor
  • [2016] Sensitivity and Uncertainty analysis of MYRRHA lead-bismuth cooled fast reactor
  • [2016] Thermal-hydraulic uncertainty propagation in a Main Steam Line Break Scenario
  • [2016] Thermal-hydraulic uncertainty propagation in a Main Steam Line Break Scenario
  • [2015] Covariances matrices of few-group homogeneized cross sections for core diffusion calculations
  • [2015] Covarianzas de las secciones eficaces homogeneizadas en dos grupos de energía para cálculos de difusión
  • [2015] European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients
  • [2015] IMPACT OF NUCLEAR DATA UNCERTAINTIES ON THE REACTIVITY OF AN ASTRID-LIKE SODIUM FAST REACTOR
  • [2015] Metodologías de propagación de incertidumbres con el código de difusión COBAYA
  • [2015] Metodologías de propagación de incertidumbres con el código de difusión COBAYA
  • [2015] SPANISH CONTRIBUTION IN THE DESIGN OF THE ALFRED REACTOR INSIDE THE ESNII+ Project
  • [2015] Spanish contribution in the design of the ASTRID reactor inside the ESNII+ Project
  • [2015] Uncertainty propagation techniques for reactor core calculations using COBAYA code
  • [2015] Uncertainty propagation techniques for reactor core calculations using COBAYA code
  • [2014] DESARROLLO DE UNA HERRAMIENTA DE VERIFICACIÓN PARA CÁLCULOS DE DIFUSIÓN MEDIANTE COBAYA
  • [2014] Desarrollo de una herramienta de verificación para cálculos de difusión mediante COBAYA
  • [2014] EFECTOS DE GENERACIÓN Y OPTIMIZACIÓN DE LIBRERÍAS DE SECCIONES EFICACES EN EL ANÁLISIS DE TANSITORIOS EN REACTORES PWR
  • [2014] Efectos de generación y optimización de librerias de secciones eficaces en ela nalisis de transitorios en reactores PWR
  • [2014] SENSITIVITY/UNCERTAINTY ANALYSIS FOR BWR CONFIGURA-TIONS OF EXERCISE I-2 OF UAM BENCHMARK
  • [2014] Student oportunities in the frame of the European Project GENTLE
  • [2013] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor Tipo de participación: Publicación: Para su publicación enLugar celebración: NY (USA) Fecha: March 4-8, 2013
  • [2013] Nuclear data uncertainty propagation to reactivity coefficients of Sodium Fast Reactor
  • [2013] Preparing Exercise I-3: Optimization of cross-section tables using sensitivity coefficients in COBAYA3 Congreso:Fecha y lugar de celebración: París, Francia. Abril 10-12, 2013
  • [2013] The Nuclear Science and Technology master at the Universidad Politecnica de Madrid
  • [2013] UPM Activities on Sensitivity and Uncertainty Analysis of Assembly Depletion Abril 10-12, 2013
  • [2012] Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project
  • [2012] Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project
  • [2012] Development of the neutronic/thermal-hydraulic coupling between COBAYA3 and SUBCHANFLOW. Aplication to Sodium Fast reactors
  • [2012] Initiatives and facilities for E&T in the nuclear science and technology master at UPM
  • [2012] Initiatives and facilities for E&T in the nuclear science and technology master at UPM
  • [2012] Optimización de librerías tabuladas de secciones eficaces mediante el empleo de coeficientes de sensibilidad
  • [2012] Optimización de librerías tabuladas de secciones eficaces mediante el empleo de coeficientes de sensibilidad
  • [2011] A proposed parameterization of interface discontinuity factors depending on neighborhood for pin-by-pin diffusion computations for LWR
  • [2011] Formación y entrenamiento de ingenieros nucleares mediante el máster de Ciencia y Tecnología nuclear de la UPM
  • [2011] Interactive graphic simulation: an advanced methodology to improve the teaching-learning process in nuclear engineering education and training
  • [2011] Interface discontinuity factors in the modal eigenspace of the multigroup diffusion matrix
  • [2011] On the extension of the analytic nodal solver ANDES to sodium fast reactors
  • [2010] Análisis de la transmutación de Actínidos Minoritarios en un reactor rápido de sodio con modelo de carga homogéneo mediante el código MCNPX-CINDER
  • [2010] Aplicación del código COBAYA3 al análisis multiescala con acoplamiento neutrónico-termohidráulico en reactores PWR
  • [2010] EDUCATION AND TRAINING OF FUTURE NUCLEAR ENGINEERS THROUGH THE USE OF AN INTERACTIVE PLANT SIMULATOR
  • [2010] Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator
  • [2009] DEVELOPMENT AND PERFORMANCE OF THE ANDES/COBRA-III COUPLED SYSTEM IN HEXAGONAL-Z GEOMETRY
  • [2009] Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
  • [2009] Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
  • [2009] Improvements in the Prediction Capability of ACAB Code to Transmutation Analysis in IFMIF
  • [2009] Improvements in the Prediction Capability of Codes Used to Design Innovative Reactors
  • [2008] Descomposición espacial en subdominios para reactores de agua ligera a la escala de la barra de combustible
  • [2008] Development of an Analytic Nodal Diffusion Solver in Multigroups for 3D Reactor Cores with Rectangular or Hexagonal Assemblies.
  • [2008] Impact of different correlation structures in cross-section covariance matrices on the inventory and inventory-related parameters
  • [2008] Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system
  • [2007] Application of Monte Carlo Techniques for Propagation of Cross Section Uncertainties to Actinide Inventory in ADS Transmuters: Comparison with Sensitivity Analysis
  • [2007] Assessment of Uncertainties in the Prediction of Actinide Inventory in Accelerator-Driven Transmutation Dedicated Systems
  • [2007] Development and Performance of the Analytic Nodal Diffusion Solver ANDES in Multigroups for 3D Rectangular Geometry
  • [2007] Effect of Activation Cross Section Uncertainties in Transmutation Analysis of Realistic Low-Activation Steels for IFMIF
  • [2007] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2007] The Integrated 3-D PWR Core Analysis System SEANAP
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• Premios
  • [2019] Pablo Romojaro, Finalista del premio 13th ENEN PhD Event & Prize 2019 a la mejor tesis doctoral (durante FISA 2019 conference, Pitesti, Romania, 4-7 junio 2019)
  • [2019] Pablo Romojaro, Premio de la SNE 2019 a la mejor Tesis Doctoral sobre Ciencia y Tecnología Nuclear
  • [2019] Premio a la mejor ponencia oral de la 45ª Reunión Anual de la SNE
  • [2019] Premio a la mejor ponencia oral de la 45ª Reunión Anual de la SNE
  • [2019] Premio a la mejor ponencia oral de la 45ª Reunión Anual de la SNE
  • [2018] Emilio Castro, Finalista del premio 12th ENEN PhD Event & Prize 2018 a la mejor tesis doctoral
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• Proyectos de I+D+i
  • [2019] CATEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
  • [2019] CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
  • [2019] CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
  • [2019] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2019] Responsable del Proyecto Propio: Desarrollo de un sistema BEPU para la simulación de reactores PWR
  • [2019] SANDA (Supplying Accurate Nuclear Data for Energy and Non-Energy Applications)
  • [2018] CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
  • [2018] ESNII PLUS( PREPARING ESNII FOR HORIZON 2020)
  • [2018] Responsable del Proyecto Propio: Desarrollo de un sistema BEPU para la simulación de reactores PWR
  • [2017] ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools
  • [2017] European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ESFR-SMART)
  • [2017] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2016] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2016] CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
  • [2016] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2015] ANDES - 249671
  • [2015] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2015] CP-ESFR: COLLABORATIVE PROJECT ON EUROPEAN SODIUM FAST REACTOR PROJECT Nº 232658
  • [2015] CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
  • [2015] NUCLEAR DATA IMPROVEMENTS AND DEVELOPMENT OF TOOLS-NUCLEAR DATA EVALUATION
  • [2014] ANDES - 249671
  • [2014] CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
  • [2014] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2014] ESNII PLUS( PREPARING ESNII FOR HORIZON 2020)
  • [2014] NURESAFE-323263
  • [2014] NURESAFE-323263
  • [2014] ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
  • [2013] CHANDA (Solving Challenge in Nuclear Data)
  • [2013] CHANDA: solving CHAllenges in Nuclear DAta
  • [2013] ESNII plus: Preparing ESNII for HORIZON 2020
  • [2013] ESNII plus: Preparing ESNII for Horizon 2020
  • [2013] GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
  • [2013] NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM
  • [2013] NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM Grant Agreement no: 323263
  • [2013] NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
  • [2011] CP-ESFR: Collaborative Project on European Sodium Fast Reactor
  • [2010] CP-ESFR: COLLABORATIVE PROJECT ON EUROPEAN SODIUM FAST REACTOR PROJECT Nº 232658
  • [2010] NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
  • [2009] CP-ESFR: Collaborative Project on the European Sodium Fast Reactor.
  • [2009] CREDITO AL QUEMADO EN LOS ANALISIS DE SEGURIDAD FRENTE A CRITICIDAD
  • [2009] NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
  • [2008] European Plataform for Nuclear Reactor Simulations NURESIM
  • [2007] European Plataform for Nuclear Reactor Simulations NURESIM
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• Responsabilidades
  • [2018] Miembro del Expert Group on Uncertainty Analysis in Modelling (EGUAM) of Working Party on Scientific Issues of Reactor Systems (WPRS)
  • [2017] Miembro del grupo de expertos de la NEA 'Expert Group on Uncertainty Analysis and Modeling' (EGUAM)
  • [2016] Responsable de la organización del seminario impartido por Rafael Mendizábal, del Cuerpo Técnico del Consejo de Seguridad Nuclear
  • [2008] Coordinadora del curso Introduction to Nuclear Energy del Programa ATHENS de la Universidad Politécnica de Madrid
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• Tesis Doctorales
  • [2019] Nuclear Data Analyses for Improving the Safety of Advanced Lead-cooled Reactors
  • [2018] Methodologies for sensitivity/uncertainty analysis using reactor core simulators with application to PWR
  • [2018] Methodologies for sensitivity/uncertainty analysis using reactor core simulators with application to PWR
  • [2017] Generación de librerias optimizadas con cuantificaccion de incertidumbres para claculos realistas de reactores nucleares de agua ligera
  • [2013] Tesis Raquel Ochoa Valero:
  • [2010] Desarrollo de un Código anatítico de difusión neutrónica en multigrupos para reactores en geometrías 3D rectangulares y Hexagonales
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