For a treatment of molten salt wastes generated from a pyroprocessing of oxide spent fuel, we had suggested a stable chemical route, named GRSS (Gel-Route Stabilization & Solidification), and a subsequent consolidation method. By using this method, a series of monolithic wasteforms with different conditions were fabricated, and then their physicochemical properties were investigated. A simulated salt containing 90wt% LiCl, 6.8wt% CsCl, and 3.2wt% SrCl2 was treated with a gel-forming material system, Si/Al/P = 0.4/0.4/0.2 and 0.35/0.35/0.3, and the gel-products were treated at 1100C° after mixing with borosilicate glass powder, where the salt loadings were about 16∼20wt%. The solidified products had a density of 2.3∼2.35g/cm3, a micro-hardness of 4.69∼4.72GPa, a glass transition temperature of 528∼537C°, and a thermal expansion coefficient of 1.65×10−7∼3.38×10−5/C°. Leaching results by the PCT-A method revealed leached rates, 10−3∼10−2g/m2day and 10−4∼10−3g/m2day for Cs and Sr, respectively. From the long-term ISO leaching test, the 900day-leached fraction of Cs and Sr predicted by a semi-empirical model were 0.89% and 0.39%. The leaching behaviors indicated that Cs would be immobilized into a Si-rich phase while Sr would be in a P-rich phase. The experimental results revealed that the GRSS method could be an alternative method for a solidification of radioactive molten salt wastes.
- Nuclear Division and Environmental Engineering Division
Characteristics of Solidified Products Containing Radioactive Molten Salt Waste
Kim, I, Park, H, Cho, Y, Kim, K, Park, S, & Kim, E. "Characteristics of Solidified Products Containing Radioactive Molten Salt Waste." Proceedings of the The 11th International Conference on Environmental Remediation and Radioactive Waste Management. 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B. Bruges, Belgium. September 2–6, 2007. pp. 315-319. ASME. https://doi.org/10.1115/ICEM2007-7303
Download citation file: