Separations Chemistry, Quarterly Progress Report, July-September 1953 (open access)

Separations Chemistry, Quarterly Progress Report, July-September 1953

"Continued progress has been made with the high temperature decontamination processes for irradiated uranium fuel. The fused salt treatment of molten uranium has been extended to UCl3. Plutonium and rare earths were extracted into the UCl3 phase. Direct plutonium distillation from molten irradiated uranium has been scaled up to the hundred gram scale. Solid scavenging experiments using uranium oxide, uranium carbide, and uranium nitride in contact with molten uranium have indicated fission product removal. A scaled-up investigation of the separation and recover of uranium from an SIR type ceramic fuel using the volatile fluoride process has indicated the feasibility of this separation method. The effect of irradiation on the decomposition of BrF3 has been further studies in experiments using the NAA statitron.'
Date: April 1, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D.
System: The UNT Digital Library