IMMOBILIZATION OF THE RADIONUCLIDES FROM SPENT ION-EXCHANGE RESINS USING VITRIFICATION

摘要

Approximately 60 g of an iron-enriched borosilicate glass was made in the radiochemical labs of the SavannahrnRiver Technology Center (SRTC). The glass was made to demonstrate the immobilization of the radioisotopesrncontained on representative Argentine ion exchange resins (similar to those used at the Embalse plant). The productrnwas approximately 90% amorphous and was quite durable as measured by the release rates from the ProductrnConsistency Test (PCT). The release rates were considerably better than those of the U. S. High Level Wastern(HLW) benchmark DWPF EA glass. The release rate of the Cs-137 was predictably similar to that of Na and Li.rnNo Co-60 or Sr-90 was measured in the PCT leachate. The mass balances for the inactive additives were quiterngood. Of the radioisotopes, approximately 71% of Cs-137 was accounted for in the glass product. This was similarrnto the Na mass balance. Approximately 89% of the Co-60 was accounted for in the glass product.