Available topics
Within the Institute for Advanced Nuclear Systems:
- A “yield” database for the future ISOL @ MYRRHA facility
- Decommissioning of medical cyclotrons: In-depth analysis of radiological inventory with regard to systems, structures and components evacuation routes acceptance (Case Study: 40 MeV CGR Cyclotron VUB (Brussels))
- Design of an integrated graphite collimator for PTF targets
- Experimental study of cavitation in liquid Lead-Bismuth Eutectic (LBE)
- Improvement of the computational scheme for performing uncertainty analysis through the ANICCA fuel cycle code
- Modelling of a multi-cycle full-core PWR depletion benchmark
- Neutronics modelling of the MYRRHA reactor with the Serpent code
- Production of important nuclides in spent nuclear fuel
- SANDY application for the analysis of nuclear data covariance
- Simulation of a “yield station” for the ISOL@MYRRHA facility
- Spent nuclear fuel sensitivity to model parameters
Within the Institute for Environment, Health and Safety:
- Cellulose degradation and nuclear waste management: characterization of cellulose degradation products by ESI-ToF-MS
- Dosimetry during microCT examination of rodents
- Risk Governance for Critical Infrastructure
Within the Institute for Nuclear Materials Science:
- Development of automatic “Help Authoring Tools” generator
- Development of webparts for the Calculation Office portals
- Research for comparing sensitivity increase of TQ-ICP-MS (Tripple quad Inductively coupled plasma mass spectrometry) versus standard ICP-MS to determine difficult nuclides such as Ca, Fe and Al.
Available topics for a BNEN thesis
Within the Institute for Advanced Nuclear Systems:
- Design of an integrated graphite collimator for PTF targets
- Experimental study of cavitation in liquid Lead-Bismuth Eutectic (LBE)
- Improvement of the computational scheme for performing uncertainty analysis through the ANICCA fuel cycle code
- Modelling of a multi-cycle full-core PWR depletion benchmark
- Neutronics modelling of the MYRRHA reactor with the Serpent code
- SANDY application for the analysis of nuclear data covariance
- Spent nuclear fuel sensitivity to model parameters
Within the Institute for Environment, Health and Safety:
Basic Information
- Domain : Nuclear Science and Technology
- Country : Belgium
- Organisation : SCK CEN
For further information visit: SCK CEN Academy