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

Technical Report · Tue Nov 13 00:00:00 EST 2018

DOI:https://doi.org/10.2172/1485264· OSTI ID:1485264

Jantzen, C. M. ^[1]

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1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

Radioactive waste sludges that were high in A_l2O₃ (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%.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC09-08SR22470
• OSTI ID: 1485264
• Report Number(s): SRNL-STI-2011-00702
• Country of Publication: United States
• Language: English

Related Subjects

mixed waste
high alumina waste
high uranium wastes
treatability study
durability testing
TCLP
durability modeling