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HOT-CELL EVALUATION OF THE GRIND--LEACH PROCESS. II. RECOVERY OF URANIUM AND THORIUM FROM IRRADIATED PYROLYTIC-CARBON-COATED SOL--GEL THORIA--URANIA PARTICLES.

Technical Report ·
DOI:https://doi.org/10.2172/4553228· OSTI ID:4553228
;

Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-22-018866
OSTI ID:
4553228
Report Number(s):
ORNL--4213
Country of Publication:
United States
Language:
English

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Related Subjects

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
THORIUM OXIDES
THORIUM/separation from spent pyrolytic-carbon-coated sol-gel oxide fuel
grind- leach process for
TIME
URANIUM
URANIUM DIOXIDE
URANIUM/separation from spent pyrolytic-carbon-coated sol-gel oxide fuel
grind-leach process for