All Topics

Within the Institute for Advanced Nuclear Systems:

• A "yield" database for the future ISOL @ MYRRHA facility
• Applicability of fracture toughness tests on ductile materials
• Design of an integrated graphite collimator for PTF targets
• Electrochemical measurement of oxygen diffusion coefficient in liquid lead-bismuth eutectic
• Finalizing PhD Study of low Prandtl number heat transfer in the E-SCAPE liquid-metal pool facility (E.Cascioli)
• Microstructural investigation of interaction LBE with austenitic stainless steel
• Simulation of a "yield station" for the ISOL@MYRRHA facility
• Studie en opmaak van een machinedossier voor een experimenteel researchapparaat
• Supporting the Primary Heat Exchanger Experimental Programme
• Étude de configurations à spectre variable dans le cœur rapide uranium/plomb de la maquette critique VENUS pour l'amélioration des données nucléaires dans le domaine épithermique: design des configurations et analyse de sensibilité.

Within the Institute for Corporate Services and Administration:

• Stage Office Management

Within the Institute for Environment, Health and Safety:

• 1. Characterisation and modelling of complex environmental problems / reactive transport modelling
• 2. Characterisation and modelling of complex environmental problems / reactive transport modelling
• 3. Characterisation and modelling of complex environmental problems / reactive transport modelling
• Application of neural networks in the analyses of gamma spectra collected during UAV flights
• Chemical and mineralogical characterization of cemented waste samples
• Diffusion of gases in desaturated clay-based materials
• External dose rates to comforters from nuclear medicine patients: a detailed computational approach
• Immobilizing problematic liquid waste in a cementitious form
• Linking the history of radiation biology evolution to the specific historical and current highlights of the radiobiology research at the Belgian Nuclear Research Centre (SCK•CEN)
• Multi-scale study of delayed ettringite formation in concrete
• Quantifying 225Ac and its daughter radionuclides in biological samples
• Risk Governance for Critical Infrastructure
• Speciation and transport of REE in Passive Treatment Systems of the Iberian Pyrite Belt

Within the Institute for Nuclear Materials Science:

• Comparison of Nitrogen and Argon Adsorption Isotherms on Nuclear Fuel
• Correlation of tensile and flexural properties of materials for fusion applications
• Design, calibration and validation of a dip tube system for nuclear tank volume measurement
• Development of a MatLab (or Python) user interface for EngInit - A tool for stress corrosion crack initiation evaluation of nickel-base alloys exposed to primary pressurized water reactor environments.
• Development of a new solvent extraction system for the separation of americium from spent nuclear fuels
• Development of automatic "Help Authoring Tools" generator
• Development of radioactive lanthanide-based nanoparticles for radiopharmaceutical applications
• Development of webparts for the Calculation Office portals
• Electrochemical oxidation of terbium towards the purification of the medical Tb-161 isotope
• Extraction behavior of radiolytic degradation compounds of methylated tetradecyl diglycolamide (mTDDGA)
• Neutron irradiation effects in ITER divertor materials
• Stability and Morphology of vacancy clusters in MAX phases
• Study of radiation-induced dimensional changes in SiO2.

Within the Service for External Medical Surveillance:

• Stage voor verpleegkundige op de arbeidsgeneeskundige dienst van het SCK CEN