Characterization of projected DWPF glasses heat treated to simulate canister centerline cooling. Revision 1

Technical Report · Tue Jun 01 04:00:00 EDT 1993

DOI:https://doi.org/10.2172/10127893· OSTI ID:10127893

Marra, S L; Jantzen, C M

Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Eventually these canistered waste forms will be sent to a geologic repository for final disposal. In order to assure acceptability by the repository, the Department of Energy has defined requirements which DWPF canistered waste forms must meet. These requirements are the Waste Acceptance Product Specifications (WAPS). The WAPS require DWPF to identify the crystalline phases expected to be present in the final glass product. Knowledge of the thermal history of the borosilicate glass during filling and cooldown of the canister is necessary to determine the amount and type of crystalline phases present in the final glass product. Glass samples of seven projected DWPF compositions were cooled following the same temperature profile as that of glass at the centerline of the full scale DWPF canister. The glasses were characterized by X-ray diffraction and scanning electron microscopy to identify the crystalline phases present. The volume percents of each crystalline phase present were determined by quantitative x-ray diffraction. The Product Consistency Test (PCT) was used to determine the durability of the heat treated glasses.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (US)
• Sponsoring Organization: USDOE, Washington, DC (US)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10127893
• Report Number(s): WSRC-TR--92-142-Rev.1; ON: DE94007281
• Country of Publication: United States
• Language: English

Related Subjects

052001
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360602
BOROSILICATE GLASS
CONTAINERS
GLASS
HEAT TREATMENTS
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
RADIOACTIVE WASTES
SCANNING ELECTRON MICROSCOPY
SPECIFICATIONS
STAINLESS STEELS
STRUCTURE AND PHASE STUDIES
VITRIFICATION
WASTE FORMS
WASTE PROCESSING
WASTES
X-RAY DIFFRACTION