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- Crystallographic data for some metal fluorides, chlorides, and oxides
- ISOCRUNCH :modifications to the CRUNCH program for the IBM 7090
- Elastic and inelastic scattering of 8- to 15-Mev deuterons from ¹¹⁴Cd :tabulated differential cross sections
- ISOPOWER :computer program for calculating power output of single radioisotope or mixed radionuclide power sources
- On the bound states of an electron in the field of a permanent electric dipole
- Electronuclear Division annual progress report :for period ending
- The effect of accommodation on thermal transpiration :limitations of the "dusty gas" model in the description of surface scattering
- A bibliography on tracer diffusion in metals :
- The ORNL book circulation control system
- Evaluation of hastelloy F and other corrosion-resistant structural materials for a continuous centrifuge in a multipurpose fuel-recovery plant
- Status and progress report on separations research and development
- Development of nondestructive testing techniques for the high flux isotope reactor fuel element
- Evaluation of thorium-base alloys for high-temperature strength
- Nuclear safety program semiannual progress report for period ending
- Abstracts of papers :water desalination information meeting, February 23-24, 1965
- Spacetime and elementary particle groups
- Orbits in a magnetic universe
- Snap-8 corrosion program quarterly progress report for period ending
- Identification of carbides, nitrides, and oxides of niobium and niobium alloys by anodic staining
- Motion of spheres in smooth rotating drums and applications to the coating of nuclear fuel particles
- Review of ORNL thermal diffusion program :January--December 1964
- Cross sections for atomic displacements in solids by fast electrons
- Alpha :a computer program for the determination of radioisotopes by least-squares resolution of the gamma-ray spectra
- Stochastic models for the distribution of radioactive material in a connected system of compartments
- Techniques for hematological studies of wild mammals
- Rare-earth halides
- Groups IV, V and VI transition metals :selected references on preparation, structure, physical properties, metallography, and transport properties.
- A comparison of first- and last-flight expectation values used in an O5R Monte Carlo calculation of neutron distributions in water
- Some calculations of the fast-neutron distribution in ordinary concrete from point and plane isotropic fission sources
- Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center :(December, 1964)
- Tabulated values of scattered gamma-ray fluxes in iron interpolated from moments-method calculations
- Survey of methods for calculating gamma-ray heating
- A comparison of three methods used to calculate gamma-ray transport in iron
- Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center :space and accelerator shielding : (November 1965)
- Behavior of iodine in reactor containment systems
- Technical Concept-Operation Henre
- Distribution of Weapons Radiation in Japanese Residential Structures
- Proceedings of Symposium on Low-Energy X- and Gamma Sources and Applications, held at Illinois Institute of Technology Research Institute, Chicago, Illinois, October 20-21, 1964
- Safety analysis of radionuclide release to the Clinch River
- Literature survey of radiochemical cross-section data below 425 MeV
- Efficiency of organic scintillators for fast neutrons
- Absolute efficiency measurements of NE-213 organic phosphors for detecting 14.4- and 2.6-MeV neutrons
- The adequacy of scale-up in experiments on fission product behavior in reactor accidents.
- A survey of empirical functions used to fit gamma-ray buildup factors
- An exponential transform as an importance-sampling device :a review / by Francis H. Clark.
- On solving systems of polynomials in several indeterminates
- List of AEC radioisotope customers with summary of radioisotope shipments, FY 1965
- Reactor yield calculations for 81 radioisotopes produced by (n,[gamma]) reactions at fluxes of 10⁷ to 10¹⁶ n/cm©ʹ²℗·sec for irradiation times of 30 minutes to one year
- The Oak Ridge National Laboratory Conceptual Design of a 250-MGD Desalination Plant
- Indexing and classification;a selected and annotated bibliography