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- Inspection of small diameter tubing by eddy-current methods
- Spherical segment with circular hole at vertex loaded axisymmetrically along the edges
- Energy and angular distribution of gamma radiation from a Co⁶⁰ source after diffusion through many mean free paths of water
- Determination of microgram quantities of carbon by low-pressure combustion
- Low-power criticality experiments on the homogeneous reactor experiement (HRE-1)
- Immersed ultrasonic inspection of pipe and tubing
- Fuel costs in single-region homogeneous power reactors
- Studies of the spherical harmonics method in neutron transport theory
- Use of ion exchange resins to concentrate radionuclides for subsequent analysis
- Hydraulic cyclones for application to homogeneous reactor chemical processing
- Some analytical solutions of the slowing down problem in hydrogen
- Tritium handling system
- The reactivity effect of an air tank against one face of the bulk shielding reactor
- Transmission of obliquely incident gamma-radiation through stratified slab barriers
- Semiannual progress report :for period ending
- Progress report on raw materials
- Semiannual progress report :for period ending
- Conference on Neutron Physics by time-of-flight, held at Gatlinburg, Tennessee, November 1 and 2, 1956.
- Radionuclides in reactor cooling water :identification, source and control
- On the relationship between the charge of an ion and its velocity
- High enrichment of uranium-235
- The solvent extraction of iron with tri-n-octylphosphine oxide
- Nuclear structure effects in internal conversion
- The preparation of thin, uniform sources for a beta-ray spectrometer
- The suspended microbiota of the Clinch River and adjacent waters in relation to radioactivity in the summer of 1956
- Radioactive waste disposal report on seepage pit liquid waste :shale column experiment
- The physics of the fused-salt reactor experiment :Oak Ridge National Laboratory
- Design study of an advanced test reactor
- Feasibility study of a homogeneous fused salt-molten metal cooled-power reactor system
- Gas cooled pebble bed reactor for a large central station
- Instrumentation and Controls Division annual progress report.
- A Compilation of data on some spectra of thorium
- An Estimation of photoneutrons from carbon-13 in an oil shield
- Nuclear process instrumentation and controls conference, held in Gatlinburg, Tennessee, May 20-22, 1958
- Uranium-235 fission-product production as a function of thermal neutron flux, irradiation time, and decay time.
- The ORNL gas-cooled reactor :materials and hazards
- Reactor controls analog facility (RCAF) operations manual
- The influence of composition upon the 1500⁰ F creep-rupture strength and microstructure of molybdenum-chromium-iron-nickel base alloys
- A Monte Carlo calculation of air-scattered gamma rays
- An investigation of the resonant properties of short exponentially and linearly tapered lines
- Operation of the ORNL graphite reactor and of the low-intensity test reactor and preoperational work on the ORR :annual report for 1956
- Proceedings of the conference on reactions between complex nuclei :Gatlinburg, Tennessee, May 5-7, 1958
- Progress report on volatility pilot plant corrosion problems to April 21, 1957
- Thermocouple research report for the period November 1, 1956 to October 31, 1957 :progress report I
- A search for Coulomb fission of U238 by 28-Mev nitrogen ions
- The application of a nominal 48 WT % U-AL alloy to plate-type aluminum research reactor fuel elements
- Plastic strain absorption as a criterion for high temperature design
- A study of the nuclear and physical properties of the ORNL graphite reactor shield
- Radiation attenuation characteristics of structural concrete
- Fitting linear combinations of exponentials to human uranium-excretion data