Portal de Transparencia

Actividad investigadora:

• Artículos en revistas
  • [2018] Evaluación de incertidumbres en parámetros tecnológicos de un núcleo PWR
  • [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
  • [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
  • [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] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
  • [2014] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
  • [2014] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
  • [2014] Propagation of Nuclear Data Uncertainties for PWR core Analysis
  ...
  mostrar más
• 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
• Estancias y sabáticos recogidos en programas oficiales
  • [2015] Estancia de colaboración para Doctorado en AREVA GmbH, Offenbach am Main, Alemania
  • [2015] Estancia de colaboración para Doctorado en PennState University, Univerisity Park, Pennsylvania, Estados Unidos de América.
• Ponencia en Congresos
  • [2018] Methodologies for Sensitivity/Uncertainty Analysis Using Reactor Core Simulators with Application to Pressurized Water Reactors
  • [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] Evaluación de incertidumbres en parámetros tecnológicos de un núcleo PWR.
  • [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] 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] 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] Improved PWR simulations by Monte-Carlo uncertainty analysis and Bayesian inference
  • [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] Uncertainty propagation techniques for reactor core calculations using COBAYA code
  • [2015] Uncertainty propagation techniques for reactor core calculations using COBAYA code
  • [2014] Propagation of U-235. U-238, Pu-239 and H in H2O nuclear data uncertainties for PWR core analysis
  • [2013] Analysis of Neutron Thermal Scattering Data Uncertainties in PWRs
  • [2013] Propagation of U235-238, Pu239 and STL Nuclear Data Uncertainties for PWR core analysis (JEF/DOC-1524)
  ...
  mostrar más
• Premios
  • [2017] Mejor ponencia de la 43ª Reunión Anual de la Sociedad Nuclear Española
• Proyectos de I+D+i
  • [2017] ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools
  • [2015] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2015] NUCLEAR DATA IMPROVEMENTS AND DEVELOPMENT OF TOOLS-NUCLEAR DATA EVALUATION
• Registros de Software
  • [2014] Thermal Scattering Libraries processed to ACE format. NEA-1883 ZZ-TSL-ACE/2013
  • [2014] Thermal Scattering Libraries processed to ACE format. RSICC DATA LIBRARY DLC-270.
• Tesis Doctorales
  • [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