Initial demonstration of DWPF process and product control strategy using actual radioactive waste
The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150{degrees}C. Process control and product quality are ensured by proper control of the melter feed composition. Algorithms have been developed to predict the processability of the melt and the durability of the final glass based on this feed composition. To test these algorithms, an actual radioactive waste contained in a shielded facility at SRS was analyzed and a frit composition formulated using a simple computer spreadsheet which contained the algorithms. This frit was then mixed with the waste and the resulting slurry fed to a research scale joule-heated melter operated remotely. Approximately 24 kg of glass were successfully prepared. This paper will describe the frit formulation, the vitrification process, and the glass durability.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10129438
- Report Number(s):
- WSRC-MS-91-012; CONF-910430-23; ON: DE92009635
- Resource Relation:
- Conference: 93. annual meeting and exposition of the American Ceramic Society (ACerS),Cincinnati, OH (United States),28 Apr - 2 May 1991; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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