Nukleær sikkerhet og pålitelighet
- Joint international program - VVER Fuel
- Round-Robin testing of fracture toughness characteristics of thin-walled tubing
- LOCA testing of high burnup PWR fuel in the HBWR. Additional PIE on the cladding of the segment 650-5
- Halden Reactor Project LOCA experiments for 2nd code benchmark
- Axial gas transport and loss of pressure after ballooning rupture of high burn-up fuel rods subjected to LOCA conditions
- Inert matrix fuels analysis by means of the Transuranus code: The Halden IFA-652 in-pile test
- Experiments for improving nuclear fuels models and performance
- Mixed-oxide (MOX) fuel performance benchmarks
- Verification of the TRANSURANUS burn-up model for WWER fuel and (U,Gd)O2 fuel
- Status and outlook for irradiation testing
- Zirconia inert matrix fuel for plutonium and minor actinides management in reactors and as an ultimate waste form
- TRANSURANUS modelling of irradiated inert matrix fuels from Halden IFA-652 experiment
- History and mission of the Halden Reactor
- Parametric study of the behaviour of a pre-irradiated BWR fuel rod under conditions of LOCA simulated in the Halden In-Pile Test System with the FALCON code
- Fuel performance experimental research
- Nuclear fuel behaviour in operational conditions and reliability
- Fuel (UO2) R&D: Needs, approaches, and results
- Zirconia inert matrix fuel for plutonium and minor actinide disposition in reactor and as ultimate waste form
- Instrument development for in-pile corrosion studies
- In-core corrosion monitoring in the Halden test reactor
