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WP3: Core component safety


In this WP the safety aspects of components in the reactor core will be investigated. The first topic is the coolability of a fuel bundle in accident scenarios by experimentally studying the effects of channel blockage. The second experiment aims to validate a buoyancy-driven control rod system that in emergency scenarios will have a safety function in the sense that it will act as a diverse backup of the nominal safety rods. Both activities will be supported by numerical simulations. The results of the work in this WP will be fed back to the safety analyses work-package 2.