Immobilization of radioactive cesium in pyrolytic-carbon-coated zeolite
All waste forms currently being developed for radwaste disposal have difficulty immobilizing cesium. A new waste form was developed to dispose of cesium by loading up to 5 wt% Cs onto zeolite granules. These zeolite particles are then heat-treated and coated with pyrolytic carbon and/or SiC to completely immobilize cesium. The leach rate of cesium from pyrocarbon-coated zeolite is 3 to 4 orders of magnitude less than for other waste forms. The authors propose that cesium be removed from the primary waste stream and loaded onto zeolite granules for subsequent coating. The total waste form (primary waste form plus coated zeolite) would have acceptable leach resistance for all radwaste components and be extremely leach-resistant for cesium. 23 references, 4 figures, 2 tables.
- Research Organization:
- Oak Ridge National Lab., TN
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7148167
- Journal Information:
- J. Am. Ceram. Soc.; (United States), Journal Name: J. Am. Ceram. Soc.; (United States) Vol. 66:6; ISSN JACTA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALKALI METAL ISOTOPES
CARBIDES
CARBON
CARBON COMPOUNDS
CESIUM ISOTOPES
CHEMICAL COATING
CHEMICAL VAPOR DEPOSITION
DEPOSITION
DISSOLUTION
ELEMENTS
HEAT TREATMENTS
HIGH-LEVEL RADIOACTIVE WASTES
INORGANIC ION EXCHANGERS
ION EXCHANGE MATERIALS
ISOTOPES
LEACHING
MANAGEMENT
MATERIALS
MINERALS
NONMETALS
PERFORMANCE TESTING
PYROLYTIC CARBON
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
RECOMMENDATIONS
SEPARATION PROCESSES
SILICON CARBIDES
SILICON COMPOUNDS
SURFACE COATING
TESTING
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
ZEOLITES