A5073525512- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Engineering Applied Research
- Cyclone Separators and Fluid Dynamics
- Graphite, nuclear technology, radiation studies
- Fusion materials and technologies
- Heat transfer and supercritical fluids
- Thermodynamic and Structural Properties of Metals and Alloys
- Hydraulic and Pneumatic Systems
- Molten salt chemistry and electrochemical processes
- Spacecraft Design and Technology
- Metallurgical Processes and Thermodynamics
- Advanced Control Systems Optimization
- Advanced Power Generation Technologies
- Radioactive element chemistry and processing
- Real-time simulation and control systems
Belgian Nuclear Research Centre
2019-2024
National Agency for New Technologies, Energy and Sustainable Economic Development
2018
University of Pisa
2010-2017
The Belgian Nuclear Research Centre (SCK•CEN) is at the forefront of heavy liquid-metal (HLM) nuclear technology worldwide with development Multi-purpose hYbrid Reactor for High-tech Applications (MYRRHA) accelerator-driven system. MYRRHA a flexible fast-spectrum pool-type research reactor cooled by lead bismuth eutectic (LBE) and has been identified as European Technology Pilot Plant lead-cooled fast reactor. Given innovative nature MYRRHA, project currently going through prelicensing...
In this work, a detailed reevaluation of past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor–type UO2 fuel rod was base irradiated in Belgian Reactor 3 up to peak pellet burnup 60 MWd/kgU. After irradiation, experienced power ramp 2, reaching terminal level 70 kW/m (later adjusted 66 kW/m). Extensive post-irradiation examination after both irradiation and experiment. experiment, cladding failure local melting...
In the framework of Gen IV Heavy Liquid Metal Fast Reactors (HLMFRs) development, research activities are carried out for improving Advanced Lead Reactor European Demonstrator (ALFRED) project. particular, functioning and safety Steam Generator Bayonet Tube (SGBT) ALFRED reactor (developed by ANSALDO Nucleare) needs to be experimentally investigated numerical tools have verified validated against reliable high quality data SGBT stationary accidental transient conditions. At ENEA CR...
Accurate prediction of steam volume fraction and the boiling crisis (either DNB or dryout) occurrence is a key safety-relevant issue. Decades experience have been built up both in experimental investigation code development qualification; however, there still large margin to improve refine modelling approaches. The qualification traditional methods (system codes) can be further enhanced by validation against high-quality data (e.g., including measurement local parameters). One these...
Abstract MYRRHA is a flexible, fast spectrum, pool type research reactor cooled by lead bismuth eutectic (LBE), under development at SCK CEN. The Primary Heat eXchangers (PHX) of are designed to operate with pressurized water as secondary coolant and located in the pool. PHX design based on double-walled bayonet tube bundle, intermediate Helium leak detection system. Three experimental facilities have been constructed CEN aim assess performance this innovative component: Leak Detection...
AbstractThis paper presents the fuel performance simulation of two past experiments that are concerned with partial melting. The activity is conducted in framework Organisation for Economic Co-operation and Development/Nuclear Energy Agency Power to Melt Maneuverability (P2M) – Second Framework Irradiation Experiments (FIDES-II) Joint ExpErimental Programme (JEEP). xM3 transient experiment involved uranium oxide (UO2) a ZIRconium Low Oxidation alloy (ZIRLO) cladding base irradiated up 27...
The present paper deals with the investigation of LFR fuel rod conceptual design proposed in European Lead cooled System project (ELSY) and Advanced Fast Reactor Demonstrator (ALFRED). Two main objectives are pursued. first one is to provide a general overview status design. focus point out comments related pellet pre-design methodologies adopted for preliminary thermo-mechanical assessment single by means pin mechanic codes.The second objective connected analysis cladding component. In long...