LOW DECONTAMINATION REPROCESSING STUDIES ON IRRADIATED URANIUM DIOXIDE REACTOR FUEL
Technical Report
·
OSTI ID:4757336
As a part of the demonstration of the reprocessingrefabricating phase for a uranium dioxide fuel cycle, 100-g quantities of oxide, irradiated to burnups as great as 15,000 Mwd/MTU, were processed. Fuel was remotely declad by oxidation, and the resulttng powder alternately oxidized in air and reduced in hydrogen. A final UO/sub 2/ powder was obtained which had properties amenable to refabrication by cold pressing and sintering. No aignificant fission product or plutonium decontamination occurred. Processing losses were less than 0.1%. No equipment or processing problems were encountered which would prevent further scaleup of the process. (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-17-004628
- OSTI ID:
- 4757336
- Report Number(s):
- NAA-SR-7136
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
Similar Records
MULTICYCLE REPROCESSING AND REFABRICATION EXPERIMENTS ON SIMULATED UO$sub 2$-FISSIA PELLETS
REPROCESSING STUDIES ON IRRADIATED URANIUM CARBIDE REACTOR FUEL
Multicycle Reprocessing and Refabrication Experiments on Sintered UO2 -Fissia Pellets
Technical Report
·
Thu Aug 30 00:00:00 EDT 1962
·
OSTI ID:4757336
REPROCESSING STUDIES ON IRRADIATED URANIUM CARBIDE REACTOR FUEL
Technical Report
·
Sun Dec 30 00:00:00 EST 1962
·
OSTI ID:4757336
+1 more
Multicycle Reprocessing and Refabrication Experiments on Sintered UO2 -Fissia Pellets
Journal Article
·
Mon Jul 01 00:00:00 EDT 1963
· Industrial and Engineering Chemistry, Process Design and Development
·
OSTI ID:4757336