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Fused salt fuel processing in the ORNL volatility pilot plant
Nonnuclear uses for depleted uranium
Operational safety of the ORNL graphite reactor using enriched-uranium fuel
A study of the kinetics of uranyl sulfate exchange with a strong base anion resin
Preparation of high-density oxides and vibratory compaction in fuel tubes
Processing of uranium carbide reactor fuels.
Recovery of uranium from amine extractants with ammonium carbonate
McCabe-Thiele graphical solution of uranium-thorium partitioning from 30% TBP-AMSCO solvent
Solvent extraction of uranium from carbonate solutions
Direct reduction of uranium hexafluoride to uranium metal by sodium :(DRUHM process)
Recovery of uranium from amines by the high nitrate-water stripping method
Further evaluation of amines as extractants for uranium from sulfate liquors
Sorption of uranium on zirconium oxide
Processes for recovery of uranium and thorium from graphite-base fuel elements.
Use of fused salt-fluoride volatility process with irradiated urania decayed 15-30 days
A comprehensive study of the neutron activation analysis of uranium by delayed-neutron counting
Recovery of irradiated uranium by a two-stage differential extraction procedure
Off-gases from the reactions of uranium carbides with nitric acid at 90⁰C
Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements
Chemical development of the 25-TBP process / J.R. Flanary, ... [et. al.].
Status and progress report on separations research and development