Abstract
Glass-based wasteforms are widely employed for the stabilization and solidification of radioactive waste. Borosilicate glasses are compositionally flexible to accommodate a wide range of waste constituents, and are of good processability, chemical durability, thermal ability, and radiation tolerance, allowing them to be the primary choice for high level radioactive waste vitrification. Nevertheless, there are also many challenging elements in the radioactive wastes that are not compatible with borosilicate glasses, which direct the development of other glass wasteforms such as phosphate glasses. In order to ensure the reliable immobilization of waste radionuclides, the resultant glass wasteforms must comply with a series of acceptance criteria for performance. Several vitrification technologies have been developed over the years and at present the Joule-heated ceramic melter, hot crucible induction-heated melter, and cold crucible induction melter are the most used commercially.
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