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- Thermal and resonance absorption cross sections of the U²³³, U²³⁵, Pu²³⁹ fission products
- The catalysis of the hydrogen-oxygen reaction by aqueous slurries of thorium oxide and thorium-uranium oxide
- Recovery of uranium and thorium from graphite fuels.
- Controlled pH stripping of uranium from amines
- Zirflex process for PWR blanket fuel :
- Recovery of uranium from DI (2-ethylhexyl) phosphoric acid (dapex) extractant with ammonium carbonate
- Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel :laboratory development
- Inline instrumentation :gamma monitor, uranium coloimeter
- Fused salt fuel processing in the ORNL volatility pilot plant
- Modified zirflex process for dissolution of 1-10% U-Zr alloy fuels in aqueous NH₄F-NH₄NO₃-H₂O₂ :laboratory development
- Processing of high-fired uranium dioxide fuels by a reduction - mercury extraction - oxidation process
- Slurry feed-pump development
- 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
- Laboratory development of the acid thorex process for recovery of Consolidated Edison Throium Reactor fuel
- 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)
- An oxyhydrochlorination process for preparing uranium-molybdenum reactor fuels for solvent extraction :laboratory development
- 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
- Chemical development of the 25-TBP process / J.R. Flanary, ... [et. al.].
- Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements
- Summary of the Kilorod Project :a semiremote 10-kg/day demonstration of ²³³UO₂-ThO₂ fuel-element fabrication by the ORNL sol-gel vibratory-compaction method
- Evidence of the absence of long-lived isotopes of promethium from fission of uranium, and the purification of promethium for the establishment of a primary spectrographic standard
- Efficiency and flow capacity of pulsed columns used for the separation of uranium from thorium by solvent extraction with di-sec-butylphenylphosphonate
- Status and progress report on separations research and development