A5019502004- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Combustion and Detonation Processes
- Risk and Safety Analysis
- Particle Dynamics in Fluid Flows
- Radioactive contamination and transfer
- Graphite, nuclear technology, radiation studies
- Fusion materials and technologies
- Cyclone Separators and Fluid Dynamics
- Aerosol Filtration and Electrostatic Precipitation
- Heat transfer and supercritical fluids
- Radioactive element chemistry and processing
- Heat Transfer and Boiling Studies
- Wind and Air Flow Studies
- Thermodynamic and Structural Properties of Metals and Alloys
- High Temperature Alloys and Creep
- Advanced Thermodynamic Systems and Engines
- Heat Transfer and Optimization
- Advanced Thermodynamics and Statistical Mechanics
- Fluid Dynamics and Mixing
- Nuclear materials and radiation effects
- Thermodynamic and Exergetic Analyses of Power and Cooling Systems
- Spacecraft and Cryogenic Technologies
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
2016-2025
Universidad Complutense de Madrid
2015-2024
Unidades Centrales Científico-Técnicas
2001-2024
Consejo de Seguridad Nuclear
2007-2021
Instituto Tecnológico de la Energía
2003
Universitat Politècnica de València
1996
The Organisation for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Benchmark Study of the Accident at Fukushima Daiichi Nuclear Power Station (BSAF), which started in 2012 continued until 2018, was one earliest responses to accident Daiichi. project, divided into two phases, addressed investigation Units 1, 2, 3 by severe (SA) codes 500 h, focusing on thermal hydraulics, core relocation, molten corium concrete interaction (MCCI), fission product release transport....
The Management and Uncertainties of Severe Accidents (MUSA) project, funded in HORIZON 2020 coordinated by CIEMAT (Spain), aims at consolidating a harmonized approach for the analysis uncertainties sensitivities associated with (SAs) focusing on Source Term (ST). In this framework, objectives Innovative Spent Fuel Pool (IMSFP – WP6), led IRSN (France), are to quantify rank affecting accident analyses (SFP), review existing contemplated SA management measures systems assess their possible...
The Great East Japan earthquake occurred on March 11, 2011, at 14:46, and the subsequent tsunami led Tokyo Electric Power Company's (TEPCO's) Fukushima Daiichi Nuclear Station (NPS) beyond a design-basis accident. After accident, Japanese government TEPCO compiled roadmap toward an early resolution to accident including, among main activities, employment improvement of existing severe (SA) computer codes. In member countries Organisation for Economic Co-operation Development/Nuclear Energy...
In the current state of maturity severe accident codes, time has come to foster systematic application Best Estimate Plus Uncertainties (BEPU) in this domain. The overall objective HORIZON-2020 project on “Management and Severe Accidents (MUSA)” is quantify uncertainties codes (e.g., ASTEC, MAAP, MELCOR, AC2) when modeling reactor spent fuel pools scenarios Gen II III designs for prediction radiological source term. To do so, different Uncertainty Quantification (UQ) methodologies are be...
The safe storage of Spent Nuclear Fuel (SNF) within a dry cask system must be guaranteed for any operating condition. In particular, the Peak Cladding Temperature (PCT) is currently employed as measure fuel integrity in normal conditions. same has to ensured also off-normal and accidental conditions by keeping PCT below regulatory limits. this regard, work proposed paper aims at evaluating performance concrete-based More specifically, influence partial complete blockage air inlet openings on...
After the Fukushima Daiichi accident, a new wave of research projects aiming at enhancing severe accident (SA) management was launched under different international frameworks. This case MUSA (Management and Uncertainties Severe Accidents), AMHYCO (Towards enhanced Accident Management H2 CO combustion risk) SOCRATES (Assessment liquid Source Term for accidental post phase), which frame H2020 HEUROPE EURATOM were devised to optimize aspects management. explored how bringing uncertainties...