Vitrification testing of simulated high-level radioactive waste at Hanford
Description
The Hanford Waste Vitrification Plant may apply vitrification technology, being developed at Pacific Northwest Laboratory, to solidify selected Hanford waste streams prior to disposal in a federal repository. Based on the first stage of flowsheet development and laboratory testing, a reference working glass and two candidate simulated feed slurries were recommended for vitrification testing. Over 500 hours of melter testing were performed in 1985 during prototype vitrification experiments. Testing demonstrated that the slurry compositions had acceptable processing characteristics in a ceramic melter. A pre-made glass-former frit was determined to be preferred as the method of glass-former addition. Due to a high chromium content in the waste, spinal crystal formation and settling occurred in the glass tank. The nature and extent of off-gas effluents were consistent with past experiments processing slurries containing formic acid
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE86012583.
Files
Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- PNL-SA--13360
Conference
- Title
- Waste management '86.
- Dates
- 2-6 Mar 1986.
- Place
- Tucson, AZ (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18002872
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOWSHEETS; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; VITRIFICATION
- Descriptors DEC
- DIAGRAMS; INFORMATION; MANAGEMENT; MATERIALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-860317--53.