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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
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