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- Dissociation and ionization of H₂⁺ by electrons and protons
- Corrosion of Volatility Pilot Plant Mark I Inor-8 hydrofluorinator and Mark III L nickel fluorinator after fourteen dissolution runs
- The angular distribution of fission fragments from the fast neutron-induced fission of U-234
- Thermodynamic properties of molten-salt solutions
- Effects of seismic vibrations on the experimental gas-cooled reactor
- Cycling of cesium-134 in white oak trees on sites of contrasting soil type and moisture
- An investigation of the corrosion resistance of brazing alloys for austenitic stainless steel fuel elements for service in 565⁰ F pressurized water
- Effect of environment on the creep properties of type 304 stainless steel at elevated temperatures
- A FORTRAN subroutine for table generation by data interpolation
- An aerodynamic-thermodynamic study of centrifugal compressors
- A generalized least squares program for the IBM 7090 computer
- IBM-7090 Gaussian integration package with optional point quadrature
- Evaluation of ultimate disposal methods for liquid and solid radioactive wastes :shipment of calcined solids
- Low temperature thermoluminescence of gamma irradiated potassium dihydrogen phosphate
- Diffusion of Zr⁹⁵ in body-centered cubic iodide zirconium
- The preparation, properties, and uses of americium-241, alpha-, gamma-, and neutron sources
- The effect of prompt neutrons on the direction and time of flight of fission fragments
- Studies of the scintillation process in CsI(Tl)
- A comprehensive study of the neutron activation analysis of uranium by delayed-neutron counting
- Fabrication and assembly of a teflon dropping-mercury electrode
- Proton recoil energy loss distribution in plane geometry
- Pulse height calculations for a parallel plate ionization chamber containing electron attaching gases
- Effects of fast-neutron irradiation and high temperature on beryllium oxide
- Nightmare :an IBM 7090 code for the calculation of gamma heating in cylindrical geometry
- In-pile-autoclave test of zircaloy-2 corrosion in UO₂(NO₃)₂ solution and of solution stability
- Calculation of the pulse-height response of NaI(Tℓ) scintillation counters
- Numerical analysis of neutron resonances
- Equipoise-3 :a two-dimensional, two-group, neutron diffusion code for the IBM-7090 computer
- An evaluation of the uranium contamination on the surfaces of alclad uranium-aluminum alloy research reactor fuel plates
- Recovery of strontium and rare earths from PUREX wastes by solvent extraction
- The twenty grand program for the numerical solution of few-group neutron diffusion equations in two dimensions
- Status report on evaluation of solid waste disposal at ORNL.
- Optical emission from irradiated thin metallic foils
- The experimental design for BeO irradiation experiments ORNL 41-8 and ORNL 41-9
- The preparation of high-purity beryllium oxide through the acetylacetone-EDTA solvent extraction process
- Feasibility studies :nondestructive testing of the Enrico Fermi Reactor Core B fuel element
- Dissolution of BeO- and Al₂O₃-base reactor fuel elements.
- Soluble neutron poisons as a primary criticality control in shielded and contained radiochemical facilities
- Aqueous processing of thorium fuels
- Production of tritium by contained nuclear explosions in salt.
- Studies of the longitudinal development of high-energy electron-photon cascade showers in copper
- A remark on the second fundamental theorem in one-velocity transport theory
- The Plasma Eater :a device to measure the rate of flow of a plasma
- Evaluation of the boron content in fuel plates fabricated for the first core loading of the Army SM-1 Reactor, formerly APPR-1
- Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending August 31, 1962
- Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
- Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962
- Reactor Chemistry Division Annual Progress Report for Period Ending January 31, 1962
- Maritime Reactor Project Annual Progress Report, November 30, 1961
- Molten-Salt Reactor Program Semiannual Progress Report, March 1 - August 31, 1961