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

Technical Report · Fri May 01 04:00:00 EDT 1992

DOI:https://doi.org/10.2172/7050984· OSTI ID:7050984

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 Preliminary 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 (PCI) was used to determine the durability of the heat-treated glasses.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 7050984
• Report Number(s): WSRC-TR-92-142; ON: DE93003325
• Country of Publication: United States
• Language: English

Related Subjects

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BOROSILICATE GLASS
COHERENT SCATTERING
CONTAINERS
COOLING
DIFFRACTION
DISSOLUTION
ELECTRON MICROSCOPY
EVALUATION
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
MANAGEMENT
MATERIALS
MICROSCOPY
NATIONAL ORGANIZATIONS
PHASE STUDIES
QUALITY ASSURANCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SAVANNAH RIVER PLANT
SCANNING ELECTRON MICROSCOPY
SCATTERING
SEPARATION PROCESSES
SPECIFICATIONS
UNDERGROUND DISPOSAL
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VITRIFICATION
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WASTES
X-RAY DIFFRACTION