2018•Unpublished venueOpen access

M-Area Mixed Waste Glasses: II: Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses

Savannah River Site (SRS), Aiken, SC (United States), C.M. Jantzen, USDOE

Abstract

Radioactive waste sludges that were high in Al2O3 (14.17 to 29.02 wt%) and U3O8 (2.93 to 5.66 wt%) while being simultaneously low in Fe2O3 (1.26 to 2.01 wt%) were vitrified into borosilicate glass in the Savannah River Site’s (SRS) M-Area. The overall Na2O concentrations of borosilicate and soda-lime-silica (SLS) glasses studied at the Savannah River National Laboratory (then the Savannah River Technology Center) prior to startup of the M-Area melter ranged from 6.80 to 27.09 wt%, while the B2O3 concentrations ranged from 0.04 to 32.62 wt%.

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Key concepts: Borosilicate glass, Uranium, Durability, Radioactive waste, Aluminium, High-level waste, Materials science, Viscosity