Laboratory-Scale Demonstration of the Fused Salt Volatility Process
Description:
The feasibility of processing enriched irradiated zirconium--uranium alloy fuel by the fused salt-fluoride volatility procedure has been demonstrated in laboratory tests with fuel having a burnup of over 10%. Uranium recoveries were greater than 99% and decontamination factors for radioactive fission products were 10/sup 6/ to 10/sup 6/. The UF/sub 6/ product contained significant quantities of nonradioactive impurities; additional work in this area is needed. (auth)
Date:
August 1, 1962
Creator:
Cathers, G. I.; Jolley, R. L. & Moncrief, E. C.
Item Type:
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Partner:
UNT Libraries Government Documents Department