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- New laboratory developments in the Zircex process
- 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
- Exact relativistic Fokker-Planck coefficients for a plasma
- Review and correlation of in-pile zircaloy-2 corrosion data and a model for the effect of irradiation
- Effect of energy degradation on the critical current in an OGRA-type device
- A phenolic resin ion exchange process for decontaminating low-radioactivity-level process water wastes
- Further evaluation of amines as extractants for uranium from sulfate liquors
- The corrosion of aluminum alloys in the Oak Ridge Research Reactor
- Radioactivity of nuclear reactor cooling fluids
- Stability of plasmas against electrostatic perturbations
- A preliminary study of the aging behavior of wrought columbium-1% zirconium alloys
- The single-scattering approximation to the gamma-ray air-scattering problem
- Removal of silica from Darex dissolver solutions
- Purification of degraded tributyl phosphate-hydrocarbon diluent solutions by distillation :status summary
- The release of Kr⁸⁵ from UO₂ in ORR capsules
- Titanium pump loop for aqueous solutions at high temperatures
- The calcination in air of beryllium oxalate trihydrate to beryllium oxide
- Cerenkov radiation intensity calculations for Sr⁹⁰ and Co⁶⁰ in water
- A study of dissolution of reactor fuels containing zirconium in a titanium vessel
- Whirlaway :a three-dimensional, two-group neutron diffusion code for the IBM 7090 computer
- Structure and use of ALGOL 60
- Evaluation of ultimate disposal methods for liquid and solid radioactive wastes.
- Use of analog computers for simulating the movement of isotopes in ecological systems
- Electrostatic ion-cyclotron plasma instabilities in a two-fluid hydrodynamic theory
- A model for fission-gas release from porous fuels in low-permeability containers
- Recording equipment for internal friction measurements
- Extraction of neptunium from acidic solutions by organic nitrogen and phosphorus compounds
- Remotely controlled shearing of pipe and structural members
- Ecological sampling and meteorological calculation of fallout on forests near Oak Ridge
- Sorption of uranium on zirconium oxide
- An investigation of the transfer of uranyl nitrate across the water-tributyl phosphate interface by the method of photographic photometry
- A study of fission product transport mechanisms in high temperature gas-cooled reactor fuel elements
- Surface preparation of metallographic specimens of zirconium-base alloys containing copper
- Photon wavelength and energy conversion tables
- INOR-8-graphite-fused salt compatibility test
- Plasma stability analysis employing equilibrium constants of motion
- Status report no. 1 on Clinch River study
- Processes for recovery of uranium and thorium from graphite-base fuel elements.
- Separation of transplutoniums from lanthanides by tertiary amine extraction
- Lid tank shielding facility measurements behind the ML-1 mockup
- Interdiffusion of helium and argon in speer moderator no. 1 graphite :(a terminal report on large-pore graphites-experimental phase)
- A survey of the hazards involved in processing liquid metal bonded fuels
- Miscellaneous experiments relating to the processing of CETR fuel by sulfex-thorex and darex-thorex processes
- Development of ring-joint flanges for use in the HRE-2
- Determinations of the kinetics and mechanisms of deboronization at 1135⁰C
- Barytes concrete for radiation shielding :mix criteria and attenuation characteristics
- The ORNL badge dosimeter and its personnel monitoring applications
- Zircex and modified zirflex processes for dissolution of 8% U-91% Zr-1% H TRIGA reactor fuel