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- Molten-salt reactor program status report
- The Oak Ridge relativistic isochronous cyclotron
- Critical mass studies.
- Monte Carlo calculations of fluxes and dose rates resulting from neutrons multiply scattered in air
- Guide to the phase diagrams of the fluoride systems
- Kinetics of the thermal decomposition of uranyl fluoride.
- High-temperature mechanical properties of Hastelloy B amd Hastelloy W
- A square-wave cyclotron oscillator
- Segregation in uranium-aluminum alloys and its effect on the fuel loading of aluminum-base fuel elements
- A summary of the separation operations
- Chemistry associated with the electromagnetic separation of chromium isotopes
- Boundary values for the inner radius of a cylindrical annular reactor
- On Kofink's approximate solution of the neutron transport equation
- High temperature pressure transmitter evaluation
- Solubility relations among some fission product fluorides in NaF-ZrF₄-UF₄ (50-46-4 mole %)
- Oxidation of uranium tetrafluoride in a moving-bed reactor
- The recrystallization and grain growth of Inconel
- Laboratory studies on the ground disposal of ORNL intermediate-level liquid radioactive wastes
- Thorex process :third uranium cycle studies
- Safeguard report for a stainless steel research reactor for the BSF (BSR-II)
- Development of the Excer process.
- Gamma-ray dose rates resulting from neutron captures in air
- Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements
- The ORNL thermonuclear program
- A modification of the spherical harmonics method in neutron transport theory
- Bremsstrahlung spectra in NaI and air
- Radiation excursions at the ORNL critical experiments laboratory.
- Some aspects of the recovery of lithium from spodumene
- Preparation and metallography of arc-melted uranium carbides
- Thermometric (enthalpymetric) titration of free acid in the presence of certain hydrolyzable ions
- Development of the Excer process.
- Development of a continuous ion exchange process for the removal and recovery of high-purity cesium from alkaline waste
- Preparation of metallographic specimens through vibratory polishing
- The use of tri-n-octylphosphine oxide in the solvent extraction of zirconium
- Comparison of pool-type reactor critical experiments with two-group and thirty-group calculations
- An evaluation of asphalt and other materials for lining radiochemical waste storage basins
- Preparation of ThO₂ for homogenous reactor blanket use
- The ORNL gas-cooled reactor :advanced concepts
- Separation of fluoride from refractory materials by fusion-pyrolysis
- Triple correlations
- Dissolution of sintered thorium-uranium oxide fuel in nitric acid-fluoride solutions
- Final report :development and testing of air-melted nickel-molybdenum alloys with minor alloying additions
- Measurement of electron flux media bombarded by x-rays
- Comparison of theoretical and experimental filtered x-ray spectra
- Solubility and stability of PuF₃ in fused alkali fluoride-beryllium fluoride mixtures
- Gas-cooled reactor project semiannual progress report for period ending ...
- Articles published in technical journals, reports published, papers presented at scientific meetins, and inventions disclosed during 1957 or ORNL staff members.
- Attenuation in Water of Radiation from the Bulk Shielding Reactor: Measurements of the Gamma-Ray Dose Rate, Fast Neutron Dose Rate, and Thermal-Neutron Flux
- Health Physics Division Annual Progress Report, July 31, 1958
- Homogeneous Reactor Project Quarterly Progress Report: November 1957-January 1958