Defense Waste Processing Facility (DWPF) Viscosity Model: Revisions for Processing High TiO2 Containing Glasses
- Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Radioactive high-level waste (HLW) at the Savannah River Site (SRS) has successfully been vitrified into borosilicate glass in the Defense Waste Processing Facility (DWPF) since 1996. Vitrification requires stringent product/process (P/P) constraints since the glass cannot be reworked once it is poured into ten foot tall by two foot diameter canisters. A unique “feed forward” statistical process control (SPC) was developed for this control rather than statistical quality control (SQC). In SPC, the feed composition to the DWPF melter is controlled prior to vitrification. In SQC, the glass product would be sampled after it is vitrified. Individual glass property-composition models form the basis for the “feed forward” SPC. The models transform constraints on the melt and glass properties into constraints on the feed composition going to the melter in order to guarantee, at the 95% confidence level, that the feed will be processable and that the durability of the resulting waste form will be acceptable to a geologic repository. The DWPF SPC system is known as the Product Composition Control System (PCCS). The DWPF will soon be receiving wastes from the Salt Waste Processing Facility (SWPF) containing increased concentrations of TiO2, Na2O, and Cs2O . The SWPF is being built to pretreat the high-curie fraction of the salt waste to be removed from the HLW tanks in the F- and H-Area Tank Farms at the SRS. In order to process TiO2 concentrations >2.0 wt% in the DWPF, new viscosity data were developed over the range of 1.90 to 6.09 wt% TiO2 and evaluated against the 2005 viscosity model. An alternate viscosity model is also derived for potential future use, should the DWPF ever need to process other titanate-containing ion exchange materials. The ultimate limit on the amount of TiO2 that can be accommodated from SWPF will be determined by the three PCCS models, the waste composition of a given sludge batch, the waste loading of the sludge batch, and the frit used for vitrification.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM)
- DOE Contract Number:
- AC09-08SR22470; AC09-96SR18500; AC09-89SR18035
- OSTI ID:
- 1323882
- Report Number(s):
- SRNL-STI-2016-00115; TRN: US1601913
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
HIGH-LEVEL RADIOACTIVE WASTES
WASTE FORMS
BOROSILICATE GLASS
WASTE PROCESSING
TITANIUM OXIDES
PROCESS CONTROL
VITRIFICATION
SAVANNAH RIVER PLANT
HARDNESS
VISCOSITY
MODIFICATIONS
LIMITING VALUES
DWPF
Salt Waste Processing Facility
monosodium titanate
crystalline silicon titanate