Portal de Transparencia

Actividad investigadora:

• Artículos en revistas
  • [2019] 3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code
  • [2019] Uncertainty and sensitivity analysis of a PWR LOCA sequence using parametric and non-parametric methods
  • [2019] Uncertainty and sensitivity analysis of a PWR LOCA sequence using parametric and non-parametric methods
  • [2018] Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant
  • [2018] Development of phenomena identification ranking table for LONF-ATWS sequences in PWR Westinghouse
  • [2018] Nuclear Communication Campaign in Spain: Basic Nuclear Fusion Course
  • [2018] Steam condensation simulation in a scaled IRWST-ADS simulator with GOTHIC 8.1
  • [2017] Analysis of the equipment and instrumentation qualification criteria using 3D containment models
  • [2017] Three-dimensional simulation of a LBLOCA in an AP1000® containment building
  • [2016] Analysis of a gas stratification break-up by a vertical jet using the GOTHIC code
  • [2016] Análisis de un accidente SBLOCA en la contención del reactor AP1000 con el código GOTHIC 8.0
  • [2016] Development of a PWR-W GOTHIC 3D model for containment accident analysis
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• Ponencia en Congresos
  • [2019] Analysis of RANS turbulence models for supercritical carbon dioxide simulation with heat transfer
  • [2019] Containment instrumentation survival under a SA with harsh pressure and temperature conditions
  • [2019] LBLOCA BEPU Analysis
  • [2018] AP1000® PASSIVE COOLING CONTAINMENT ANALYSIS OF A DOUBLE-ENDED LBLOCA WITH A 3D GOTHIC MODEL
  • [2018] Desarrollo de un modelo 3D de contención de la Central Nuclear de Trillo mediante un proceso de modelización optimizado
  • [2018] Updating of Almaraz NPP containment models with GOTHIC 8.2 QA
  • [2017] AP1000® Passive Cooling Containment Analysis With Computational Fluid Dynamics Codes
  • [2017] El seminario en seguridad nuclear de reactores avanzados como herramienta de divulgación de la tecnología nuclear
  • [2017] Simulación de la condensación de vapor en un test experimental a escala del sistema ADS del reactor AP1000® con GOTHIC 8.1
  • [2016] DEVELOPMENT OF ALMARAZ NPP AND TRILLO NPP CONTAINMENT 3D MODEL WITH THE GOTHIC CODE FOR THERMAL-HYDRAULIC ANALYSIS.
  • [2016] Double-Ended LBLOCA Containment Analysis in Trillo NPP with GOTHIC 8.1
  • [2016] Simulation of a SBLOCA and LBLOCA in a AP1000 containment with the GOTHIC code'
  • [2016] Three-dimensional Containment Accident Analysis using different approaches in Almaraz NPP
  • [2016] Three-dimensional simulation of a LBLOCA in an AP1000® containment building
  • [2016] Three-dimensional simulation of a LBLOCA in an AP1000® containment building
  • [2016] Validation and application of Almaraz NPP model. Power uprate and TRACE5 Patch1 to Patch4 transition
  • [2015] Estudio termo-hidráulico de los patrones de flujo tridimensional en las contenciones de C.N. Almaraz y C.N. Trillo con el código GOTHIC en un accidente tipo LBLOCA
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• Proyectos de I+D+i
  • [2019] Cooperative Severe Accident Research Program (CSARP)
  • [2019] PASSIVE ISOLATION CONDENSER (PIACE)
  • [2019] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2019] SAFETY ANALYSIS FOR VVER-1200 REACTORS
  • [2017] ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools
  • [2017] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
  • [2016] ANÁLISIS DEL RIESGO DE COMBUSTIÓN DE HIDRÓGENO EN LA TUBERÍA DEL VENTEO FILTRADO DE LA C.N. COFRENTES
  • [2016] Desarrollo de la tubería de venteo filtrado para la central nuclear de Cofrentes
  • [2016] PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
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• Tesis Doctorales
  • [2017] Analysis and improvement of hydrogen mitigation strategies during a severe accident in nuclear reactor containments