The relationship between glass viscosity and composition: A first principles model for vitrification of nuclear waste
Conference
·
OSTI ID:5671847
540The Defense Waste Processing Facility will incorporate high-level liquid waste into borosilicate glass for stabilization and permanent disposal in a geologic repository. The viscosity of the melt determines the rate of melting of the raw feed, the rate of gas bubble release due to foaming and fining, the rate of homogenization, and thus, the quality of the glass produced. The viscosity of the glass is in turn, a function of both glass composition and temperature. A model describing the viscosity dependence on composition, temperature, and glass structure (bonding) has been derived for glasses ranging from pure frits to frit plus 35 wt % simulated waste. 17 refs., 37 figs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5671847
- Report Number(s):
- WSRC-MS-90-41; CONF-900407-9; ON: DE92009658
- Resource Relation:
- Conference: 92. annual meeting of the American Ceramic Society, Dallas, TX (United States), 22-26 Apr 1990
- Country of Publication:
- United States
- Language:
- English
Similar Records
The relationship between glass viscosity and composition: A first principles model for vitrification of nuclear waste
The Impacts of Uranium and Thorium on the Defense Waste Processing Facility (DWPF) Viscosity Model
Defense Waste Processing Facility (DWPF) Viscosity Model: Revisions for Processing High TiO2 Containing Glasses
Conference
·
Mon Dec 31 00:00:00 EST 1990
·
OSTI ID:5671847
The Impacts of Uranium and Thorium on the Defense Waste Processing Facility (DWPF) Viscosity Model
Technical Report
·
Mon Feb 28 00:00:00 EST 2005
·
OSTI ID:5671847
Defense Waste Processing Facility (DWPF) Viscosity Model: Revisions for Processing High TiO2 Containing Glasses
Technical Report
·
Tue Aug 30 00:00:00 EDT 2016
·
OSTI ID:5671847
Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
BOROSILICATE GLASS
VISCOSITY
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
CHEMICAL COMPOSITION
TEMPERATURE DEPENDENCE
GLASS
MATERIALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
WASTES
052001* - Nuclear Fuels- Waste Processing
360606 - Other Materials- Physical Properties- (1992-)
36 MATERIALS SCIENCE
BOROSILICATE GLASS
VISCOSITY
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
CHEMICAL COMPOSITION
TEMPERATURE DEPENDENCE
GLASS
MATERIALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
WASTES
052001* - Nuclear Fuels- Waste Processing
360606 - Other Materials- Physical Properties- (1992-)