Coating of crystalline nuclear waste forms to improve inertness
Journal Article
·
· J. Am. Ceram. Soc.; (United States)
OSTI ID:5514572
Microspheres of a crystalline waste form prepared by sol-gel processing were successfully coated with layers of pyrolytic carbon and silicon carbide to isolate the radioactive wastes from the biosphere. A separate process for cesium immobilization was developed, which loads 5 wt% Cs onto zeolite particles for subsequent coating. Pyrolytic carbon-coated particles showed leach rates approx. =2 to 4 orders of magnitude less than the candidate reference borosilicate glass waste form. Aqueous leach-test results of coated waste forms were below detection limits of such sensitive analytical techniques as atomic absorption and inductively coupled plasma atomic emission.
- Research Organization:
- Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37830
- OSTI ID:
- 5514572
- Journal Information:
- J. Am. Ceram. Soc.; (United States), Journal Name: J. Am. Ceram. Soc.; (United States) Vol. 65:8; ISSN JACTA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Coating of crystalline nuclear waste forms to improve inertness
Coating crystalline nuclear waste forms to improve inertness
Immobilization of radioactive cesium in pyrolytic-carbon-coated zeolite
Journal Article
·
Sun Aug 01 00:00:00 EDT 1982
· Am. Ceram. Soc. Bull.; (United States)
·
OSTI ID:5993833
Coating crystalline nuclear waste forms to improve inertness
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:5087604
Immobilization of radioactive cesium in pyrolytic-carbon-coated zeolite
Journal Article
·
Wed Jun 01 00:00:00 EDT 1983
· J. Am. Ceram. Soc.; (United States)
·
OSTI ID:7148167
Related Subjects
052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
360605 -- Materials-- Radiation Effects
ABSORPTION SPECTROSCOPY
ALKALI METALS
BOROSILICATE GLASS
CARBIDES
CARBON
CARBON COMPOUNDS
CESIUM
COMPARATIVE EVALUATIONS
DEPOSITION
DETECTION
DISSOLUTION
ELEMENTS
EMISSION SPECTROSCOPY
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
INORGANIC ION EXCHANGERS
ION EXCHANGE MATERIALS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
METALS
MICROSPHERES
MINERALS
NONMETALS
PROCESSING
PYROLYTIC CARBON
RADIATION DETECTION
RADIATION EFFECTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOACTIVITY TRANSPORT
SEPARATION PROCESSES
SILICON CARBIDES
SILICON COMPOUNDS
SPECTROSCOPY
SURFACE COATING
TESTING
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
ZEOLITES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
360605 -- Materials-- Radiation Effects
ABSORPTION SPECTROSCOPY
ALKALI METALS
BOROSILICATE GLASS
CARBIDES
CARBON
CARBON COMPOUNDS
CESIUM
COMPARATIVE EVALUATIONS
DEPOSITION
DETECTION
DISSOLUTION
ELEMENTS
EMISSION SPECTROSCOPY
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
INORGANIC ION EXCHANGERS
ION EXCHANGE MATERIALS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
METALS
MICROSPHERES
MINERALS
NONMETALS
PROCESSING
PYROLYTIC CARBON
RADIATION DETECTION
RADIATION EFFECTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOACTIVITY TRANSPORT
SEPARATION PROCESSES
SILICON CARBIDES
SILICON COMPOUNDS
SPECTROSCOPY
SURFACE COATING
TESTING
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
ZEOLITES