Defense waste processing facility (DWPF) liquids model: revisions for processing higher 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. This report documents the development of revised TiO2, Na2O, Li2O and Fe2O3 coefficients in the SWPF liquidus model and revised coefficients (a, b, c, and d).
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC09-08SR22470; AC09-96Sr18500; AC09-89SR18035
- OSTI ID:
- 1361659
- Report Number(s):
- SRNL-STI-2017-00016
- Country of Publication:
- United States
- Language:
- English
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