Nukleær sikkerhet og pålitelighet
- Instrument capabilities and developments at the Halden reactor project
- Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code
- Experimental investigation of irradiation creep and growth of recrystallized Zircaloy-4 guide tubes pre-irradiated in PWR
- Review of instrumentation for irradiation testing of nuclear fuels and materials
- Feasibility of performing pool-side fission gas release measurements on fuel rods with short decay time
- Innovative fuel development in Ulba (Kazakhstan) and testing in the Halden reactor
- Recommendations for the conditioning of spent metallic uramium fuel and aluminium clad fuel for interim storage and disposal
- Comparison of in-reactor creep and stress relaxation of cold worked 316 and solution annealed 304L stainless steels in thermal and fast neutron spectrum reactors
- Role of Halden Reactor Project for world-wide nuclear energy development
- Upgrading of the Halden Reactor experimental capabilities for innovative fuel and material testing
- Experimental investigation of irradiation creep and growth of recrystallized Zircaloy-4 guide tubes pre-irradiated in PWR
