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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
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