Abstract

At research centres, test programs generate very particular waste forms, which cannot be treated using the known regular scenario’s and procedures, and therefore special studies need to evaluate safe handling of these special waste forms. This paper describes how a joint effort between the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, the Belgian Waste Treatment and Storage Facility Belgoprocess, and the Belgian Nuclear Research Centre worked out solutions for the 1st beryllium moderator of the BR2 and the highly activated internal parts of the BR3. The current position regarding activated graphite and aluminium is also summarised.

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