Development of High Alumina Glass Property Data for Hanford High-Level Waste Glass Models - 16231

Conference · Fri Jul 01 04:00:00 EDT 2016

OSTI ID:22838096

Vienna, John D.; Schweiger, Michael J.; Bonham, Charles C.; Lang, Jesse B.; McCarthy, Benjamin P.; Chou, Yeong-Shyung; Cooley, Scott K.; Mayer, Jodi L.; Gervasio, Vivianaluxa ^[1]; Kruger, Albert A. ^[2]

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1. Pacific Northwest National Laboratory, Richland, WA (United States)
2. U.S. Department of Energy, Office of River Protection, Richland, WA (United States)

Roughly half of the projected Hanford high-level waste batches will have waste loadings limited by relatively high concentration of Al{sub 2}O{sub 3}. Individual glasses have been formulated and tested to demonstrate that it is possible to increase the loading of these high-Al{sub 2}O{sub 3} wastes in glass by as much as 50%. To implement such increases in waste loading in the Hanford Tank Waste Treatment and Immobilization Plant, the impact of composition on the properties of high-Al{sub 2}O{sub 3} waste glasses must be quantified in the form of validated glass property-composition models. To collect the data necessary for glass property-composition models, a multi-phase experimental approach was developed. In the first phase of the study, a set of 46 glass compositions were statistically designed to most efficiently backfill existing data in the composition region for high-Al{sub 2}O{sub 3} (15 to 30 wt%) waste glasses. The glasses were fabricated and key glass properties were tested: - Product Consistency Test (PCT) on quench (Q) and canister centerline cooled (CCC) samples - Toxicity Characteristic Leaching Procedure (TCLP) on Q and CCC samples - Crystallinity as a function of temperature (T) at equilibrium and of CCC samples - Viscosity and electrical conductivity as a function of T The measured properties of these glasses were compared to predictions from previously existing models developed over lower Al{sub 2}O{sub 3} concentration ranges. Areas requiring additional testing and modeling were highlighted. (authors)

• Research Organization: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
• OSTI ID: 22838096
• Report Number(s): INIS-US--19-WM-16231
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALUMINIUM OXIDES
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONCENTRATION RATIO
ELECTRIC CONDUCTIVITY
FORECASTING
GLASS
HANFORD ENGINEERING DEVELOPMENT LABORATORY
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
RADIOACTIVE WASTE PROCESSING
TANKS
TEMPERATURE DEPENDENCE
TOXICITY
VISCOSITY