High-temperature vitrification of Hanford residual-liquid waste in a continuous melter
Over 270 kg of high-temperature borosilicate glass have been produced in a series of three short-term tests in the High-Temperature Ceramic Melter vitrification system at PNL. The glass produced was formulated to vitrify simulated Hanford residual-liquid waste. The tests were designed to (1) demonstrate the feasibility of utilizing high-temperature, continuous-vitrification technology for the immobilization of the residual-liquid waste, (2) test the airlift draining technique utilized by the high-temperature melter, (3) compare glass produced in this process to residual-liquid glass produced under laboratory conditions, (4) investigate cesium volatility from the melter during waste processing, and (5) determine the maximum residual-liquid glass production rate in the high-temperature melter. The three tests with the residual-liquid composition confirmed the viability of the continuous-melting vitrification technique for the immobilization of this waste. The airlift draining technique was demonstrated in these tests and the glass produced from the melter was shown to be less porous than the laboratory-produced glass. The final glass produced from the second test was compared to a glass of the same composition produced under laboratory conditions. The comparative tests found the glasses to be indistinguishable, as the small differences in the test results fell within the precision range of the characterization testing equipment. The cesium volatility was examined in the final test. This examination showed that 0.44 wt % of the cesium (assumed to be cesium oxide) was volatilized, which translates to a volatilization rate of 115 mg/cm/sup 2/-h.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5325867
- Report Number(s):
- PNL-3343
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALKALI METALS
BOROSILICATE GLASS
CESIUM
DATA
ELEMENTS
EXPERIMENTAL DATA
GLASS
HANFORD RESERVATION
INFORMATION
LIQUID WASTES
MANAGEMENT
MATERIALS TESTING
METALS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PHYSICAL PROPERTIES
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
US DOE
US ERDA
US ORGANIZATIONS
VERY HIGH TEMPERATURE
VISCOSITY
VITRIFICATION
VOLATILITY
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALKALI METALS
BOROSILICATE GLASS
CESIUM
DATA
ELEMENTS
EXPERIMENTAL DATA
GLASS
HANFORD RESERVATION
INFORMATION
LIQUID WASTES
MANAGEMENT
MATERIALS TESTING
METALS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PHYSICAL PROPERTIES
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
US DOE
US ERDA
US ORGANIZATIONS
VERY HIGH TEMPERATURE
VISCOSITY
VITRIFICATION
VOLATILITY
WASTE MANAGEMENT
WASTE PROCESSING
WASTES