Vitrification of HLW generated by a production unit for radiopharmaceuticals using simulated waste solutions

This study deals with durable borosilicate glasses for the immobilizing of radioisotopes from nuclear waste streams generated by a radiopharmaceutical production unit. In this regard, different boron frits (glasses) and waste-loaded glasses were prepared under various experimental conditions. The effects of some parameters such as melting temperature, cooling procedure and various raw materials were investigated. The best composition of the frits as well as the best glass/waste ratio was determined to optimize the immobilization process. All experiments were performed in non-active bench scale.