A5000737543- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Radioactive element chemistry and processing
- Thermodynamic and Structural Properties of Metals and Alloys
- Nuclear and radioactivity studies
- Heat transfer and supercritical fluids
- Nuclear Physics and Applications
Belgian Nuclear Research Centre
2022-2024
University of Cambridge
2022
Minor actinides are the main contributors to medium- and long-term radiotoxicity heat production in spent nuclear fuels. Research efforts currently ongoing explore different options dispose of such radionuclides, e.g., their burning fast reactors within mixed-oxide The MYRRHA sub-critical reactor is one future facilities with envisaged transmutation capabilities. This work assesses thermal–mechanical performance a homogeneous Am-bearing fuel pin both In-Pile test Section position "Revision...
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...
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...
Minor actinides are the main contributors to medium- and long-term radiotoxicity heat production in spent nuclear fuels. Research efforts currently ongoing explore different options dispose of such radionuclides, e.g., their burning fast reactors within mixed-oxide The MYRRHA sub-critical reactor is one future facilities with envisaged transmutation capabilities. This work assesses thermal-mechanical performance a homogeneous Am-bearing fuel pin both In-Pile test Section position “Revision...