Nukleær sikkerhet og pålitelighet
- Irradiation creep and irradiation stress relaxation of 316 and 304L stainless steel
- FUMEX-III: A new IAEA coordinated research project on fuel modelling at extended burnup
- Comparative study of inert matrix fuel concepts from IFA-652 experiment
- Changes of the surface-to-volume ratio and diffusion coefficient of fission gas in fuel pellets during irradiation
- Integral approach to innovative fuel and material investigations in the Halden Reactor
- LOCA - experiment med högutbränt bränsle i Haldenprogrammet
- Fuel behaviour modelling - basic principles and related data
- Recent results from the Halden Reactor Project LOCA experiment programme
- Crud formation on low duty PWR fuel in the Halden Reactor
- Irradiation test of MOX fuel rods fabricated by attrition-milling and analysis of in-pile data with cosmos mode
- In-core fuel performance and material characterization in the Halden Reactor
- Application of research reactors to irradiation testing of nuclear fuels and materials
- Under irradiation issues of the CSZ–based inert matrix fuels from IFA-652 Halden experiment
- Fuel performance beyond design - Exploring the limits
- Behavior of homogeneous and heterogeneous MOX fuel
