HOT-CELL EVALUATION OF THE GRIND--LEACH PROCESS. II. RECOVERY OF URANIUM AND THORIUM FROM IRRADIATED PYROLYTIC-CARBON-COATED SOL--GEL THORIA--URANIA PARTICLES
- Author
- Goode, J. H.
- Published
- United States : [publisher not identified], 1968.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1968. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Flanary, J. R.
- Report Numbers
- ORNL-4213
- Other Subject(s)
- Carbon
- Catalysis
- Coating
- Colloids
- Efficiency
- Fission products/separation from spent pyrolytic-carbon-coated sol-gel oxide fuel, grind-leach process for
- Fluorides
- Hot cells
- Leaching
- Machining
- N20510 -chemistry-radiochemistry & nuclear chemistry- reactor fuel processing
- Nitric acid
- Particles
- Radiation protection
- Reactor fuel elements/reprocessing of pyrolytic-carbon-coated sol-gel oxide, evaluation of grind-leach
- Remote handling
- Sol-gel process
- Storage
- Thorium oxides
- Thorium
- Thorium/separation from spent pyrolytic-carbon-coated sol-gel oxide fuel, grind- leach process for
- Time
- Uranium dioxide
- Uranium
- Uranium/separation from spent pyrolytic-carbon-coated sol-gel oxide fuel, grind-leach process for
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: W-7405-ENG-26
NSA number: NSA-22-018866
OSTI Identifier 4553228
Research organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States).
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