Laboratory-Scale Demonstration of the Fused Salt Volatility Process

G. I. Gathers; R. L. Jolley; E. G Moncrief

doi:dx.doi.org/10.13182/NSE62-A26182

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Home / Publications / Journals / Nuclear Science and Engineering / Volume 13 / Number 4

Laboratory-Scale Demonstration of the Fused Salt Volatility Process

G. I. Gathers, R. L. Jolley, E. G Moncrief

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 391-397

Technical Paper / dx.doi.org/10.13182/NSE62-A26182

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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 10⁶ to 10⁹. The UF₆ product contained significant quantities of nonradioactive impurities; additional work in this area is needed.