Projects

Corrosion and hydriding (H2 uptake) in different cladding materials
High priority is given to the development of new fuel cladding materials that exhibit improved reliability and safety margins under reactor operation. Experimental evidence is required showing that the material has improved corrosion behaviour compared with other available materials.
Effects of alloying elements on the stress corrosion cracking resistance
During exposure to a radiation environment, the mechanical and microstructural properties of a material will change. The materials become harder and more brittle and the microstructure evolves in such a way as to make the material potentially more susceptible to cracking.
Investigation of fission gas release in fuel
When fuel rods are irradiated, gas is generated through the fission process. When 10 000 kWh of energy is produced, 12 - 13 cm3 of gas, primarily the noble gases xenon and krypton, will be formed.Most of the gas that is generatedremains within the fuel, but some is released (through diffusion) to the internal volumes in the fuel rods (which are designed to enable incorporation of the released gas).
Investigation of fuel with additives
Many nuclear power plants are currently being operated with 18-month fuel cycles rather than the 12-month cycles that were normal previously. Fuel undergoes both structural and volumetric changes during irradiation, which in turn influences its behaviour under different operating conditions, and in particular at high burn-ups (longer operating cycles).
Study of dynamic fuel rod behaviour under rapid power changes
Locally, in reactor cores, parts of fuel rods may be subjected to periodic power variations as well as stepwise changes in heat load. It is important to know how quickly and to what extent fuel rods react under such operating conditions.
Investigations of fuel rod behaviour under simulated loss-of-coolant (LOCA) conditions.
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