Portal de Transparencia

Actividad investigadora:

• Artículos en revistas
  • [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] Uncertainty quantification: parametric methods assessment
  • [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] 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
  • [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] Selected Papers from OECD-NEA PSBT Benchmark
  • [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] Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases
  • [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
  • [2010] A domain decomposition methodology for pin by pin coupled neutronic and thermal-hydraulic analyses in COBAYA3
  • [2009] A domain decomposition methodology for pin by pin coupled neutronic and thermal-hydraulic analyses in COBAYA3
  • [2008] Participación española en el desarrollo de la Plataforma Europea para Simulación de Reactores Nucleares (NURESIM)
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• 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
• Otras Publicaciones
  • [2008] ”Integration of ANDES and COBAYA in SALOME”
  • [2008] Subproject Multi-physics (SP3) Deliverable D3.4 COBAYA3 Integration within the SALOME Platform
• Ponencia en Congresos
  • [2019] Active learning in reactor physics using state-of-the-art simulation tools at Universidad Politécnica de Madrid
  • [2019] Metodologías de cuantificación de incertidumbre . Benchmark UAM Fase II Ejercicio 5A - PSBT
  • [2018] Neutronic and thermal-hydraulic uncertainty propagation in coupled multiphysics. Neutronic uncertainty effect
  • [2018] Neutronic and thermal-hydraulic uncertainty propagation in coupled multiphysics. Neutronic uncertainty effect.
  • [2017] Análisis de la incertidumbre en la geometría de la barra combustible y en los modelos mediante la aplicación del sistema DAKOTA/COBRA-TF al ejercicio de la OCDE/NEA Uncertainy Analysis in Best-Estimate Modelling (UAM)
  • [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] 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] COMPARISON OF SUBCHANNEL AND AVERAGED CHANNEL THERMAL-HYDRAULIC DESCRIPTIONS ON COUPLED PIN-BY-PIN NEUTRONIC CALCULATIONS
  • [2016] COMPARISON OF SUBCHANNEL AND AVERAGED CHANNEL THERMAL-HYDRAULIC DESCRIPTIONS ON COUPLED PIN-BY-PIN NEUTRONIC CALCULATIONS
  • [2016] Efecto de la nodalización neutrónica en el análisis de seguridad de un transitorio MSLB PWR
  • [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] Preparing uncertainty quantification in multi-physics and multi-scale core simulations using COBAYA and CTF codes
  • [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] Acoplamiento de COBAYA4 con la nueva versión de COBRATF
  • [2015] Acoplamiento independiente y automático entre códigos Neutrónicos y Termohidráulicos
  • [2014] CÁLCULOS DE DIFUSIÓN 3D EN MULTIGRUPOS DE REACTORES LWR MEDIANTE EL USO DE GPU
  • [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
  • [2013] The Nuclear Science and Technology master at the Universidad Politecnica de Madrid
  • [2013] UPM activities: Neutronic/Thermohydrulic (COBRA-TF) coupling and Inventory prediction using SCALE6.1 Congreso: Fecha y lugar de celebración: Salamanca, Spain. 19-20 February 2013
  • [2012] ANÁLISIS DE UN ACCIDENTE SGTR MEDIANTE LA UTILIZACIÓN DEL SIMULADOR GRÁFICO INTERACTIVO DE ZORITA (SGIZ)
  • [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] 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
  • [2011] ASSESSMENT OF CTF BOILING TRANSITION AND CRITICAL HEAT FLUX MODELING CAPABILITIES USING THE OECD/NRC BFBT AND PSBT BENCHMARK DATABASES
  • [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] The Key Role Transferring Knowledge Of Nuclear España, The Spanish Nuclear Society Magazine?
  • [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
  • [2010] Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code
  • [2008] Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis
  • [2008] Descomposición espacial en subdominios para reactores de agua ligera a la escala de la barra de combustible
  • [2007] Multiscale and Multiphysics Coupling in COBAYA3
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• Proyectos de I+D+i
  • [2019] CATEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
  • [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
  • [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] GRADUATE AND EXECUTIVE NUCLEAR TRAINING AND LIFELONG EDUCATION- GENTLE
  • [2017] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2016] CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
  • [2016] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2015] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2015] CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
  • [2015] ISAMAR: Aplicación de la Metodología de Análisis integrado de la seguridad a reactores nucleares avanzados
  • [2015] Proyecto ISAMAR (Integrated Safety Assessment Methodology Applied to Advanced Reactors)
  • [2014] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2014] GRADUATE AND EXECUTIVE NUCLEAR TRAINING AND LIFELONG EDUCATION- GENTLE
  • [2014] NURESAFE-323263
  • [2014] NURESAFE-323263
  • [2014] ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
  • [2013] Desarrollo de una plataforma multifisica de altas prestaciones para simulaciones termohidraulico-neutronicas en ingenieria nuclear
  • [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
  • [2012] NUC-MULTPHYS.: Desarrollo de una Plataforma Multifísica de Altas Prestaciones para Simulaciones Termohidráulico-Neutrónicas en Ingeniería Nuclear.
  • [2010] NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
  • [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 Multi-physics Experimental Data, Benchmarks and Validation (EGMPEBV)
  • [2017] : Miembro del grupo de expertos de la NEA 'Expert Group on Multi-physics Experimental Data, Benchmarking and Validation' (EGMPEBV)
  • [2008] Coordinadora del curso Introduction to Nuclear Energy del Programa ATHENS de la Universidad Politécnica de Madrid
  • [2008] Miembro de la Comisión de Publicaciones de la Sociedad Nuclear Española
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• Tesis Doctorales
  • [2019] Study and implementation of neutronic-thermohydraulic coupling methods for detailed analysis transients in nuclear reactors for safety margins optinmization
  • [2010] Desarrollo e implementación de la descomposición en subdominios del acoplamiento neutrónico-termohidráulico mediante disecciones alternadas con un sistema de cálculo multiescala