HOT-CELL EVALUATION OF THE BURN--LEACH METHOD FOR REPROCESSING IRRADIATED GRAPHITE-BASE HTGR FUELS.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-24-013997
- OSTI ID:
- 4760236
- Report Number(s):
- ORNL-4120
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-70
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
N38700 -Reactor Components
Fuels & Accessories
COMBUSTION
FUELS
GAS COOLANT
GRAPHITE
HOT CELLS
LEACHING
RADIATION PROTECTION
REACTORS
REMOTE HANDLING
REPROCESSING
SEPARATION PROCESSES
THORIUM
URANIUM
THORIUM/separation from graphite-base HTGR fuel
hot- cell evaluation of burn-leach method for
REACTOR FUELS/reprocessing of graphite- base HTGR
hot-cell evaluation of burn-leach method for
REACTORS
GAS-COOLED/ fuels for
burn-leach method for reprocessing of graphite base
URANIUM/ separation from graphite-base HTGR fuel
hot-cell evaluation of burn-leach method for
N38700 -Reactor Components
Fuels & Accessories
COMBUSTION
FUELS
GAS COOLANT
GRAPHITE
HOT CELLS
LEACHING
RADIATION PROTECTION
REACTORS
REMOTE HANDLING
REPROCESSING
SEPARATION PROCESSES
THORIUM
URANIUM
THORIUM/separation from graphite-base HTGR fuel
hot- cell evaluation of burn-leach method for
REACTOR FUELS/reprocessing of graphite- base HTGR
hot-cell evaluation of burn-leach method for
REACTORS
GAS-COOLED/ fuels for
burn-leach method for reprocessing of graphite base
URANIUM/ separation from graphite-base HTGR fuel
hot-cell evaluation of burn-leach method for