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- Recursion relations and simplified expressions for the 6-j symbols
- Annealing of gamma ray induced changes in antimony doped germanium
- A CDC-1604 subroutine package for making linear, logarithmic and semilogarithmic graphs using the CALCOMP plotter
- Corrosion mechanisms in refractory metal-alkali metal systems
- Pump loops used for materials testing in high temperature aqueous solutions and slurries
- Heat transfer from spent reactor fuels during shipping :a proposed method for predicting temperature distribution in fuel bundles and comparison with experimental data
- Fixation of fission products in aluminum nitrate wastes by ceramic masses
- Fabrication development of U-Mo-UO₂ and U-Mo-UC dispersion fuels for the Enrico Fermi fast-breeder reactor
- Tests of high-efficiency filters and filter installations at ORNL
- Equipment for hardness testing at elevated temperatures
- Evaluation of ultimate disposal methods for liquid and solid radioactive wastes.
- Thermoluminescence spectra and activation energies for aromatic amino acids, trypsin, and spores of Bacillus megaterium.
- Engineering features of DCX-2
- Research materials information center bulletin.
- A study of the shield of the Virginia Polytechnic Institute UTR-10 reactor
- Regional water supply by nuclear desalination
- Effect of particle agglomeration on the penetration of filters utilized with double containment systems
- Molten-Salt Reactor Program Semiannual Progress Report, July 31, 1963
- Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962
- Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962
- Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963
- Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending January 31, 1963
- Thermonuclear Project Semiannual Report For Period Ending October 31, 1962
- A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator
- Nuclear theory index.
- Oak Ridge Metals and Ceramics Division Annual Progress Report: 1963
- Army Reactors Program Annual Progress Report: 1962
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1963
- Nuclear cross section program at ORN :February 15, 1963 - August 1, 1963
- General Correlative Studies - Operation Bren
- Neutron Physics Division Annual Progress Report, September 1, 1962
- Conversion of simulated high-level radioactive waste solutions to glassy solids in a pot by a rising liquid level method :the RL-Potglass process
- Equilibrium distribution of metal-ion complexes
- An investigation of the influence of the holdup effect of double containment on reactor hazards
- Handbook of shielding requirements and radiation characteristics of isotopic power sources for terrestrial, marine, and space applications
- The herpetofauna of the Oak Ridge area
- Fabrication development of U₃O₈-aluminum composite fuel plates for the advanced test reactor
- Elastic and inelastic scattering of 5- to 13.5-Mev deuterons from Ni⁶⁰ :tabulated differential cross sections
- The nucleon transport code, NTC
- Pulse-height spectra of gamma rays emitted by the stainless-steel-clad bulk shielding reactor II (BSR-II)
- A study of the response contours of the hot-pressed density of thorium oxide pellets
- Review of ORNL thermal diffusion program January-December 1963
- Diffusion of titanium-44 and vanadium-48 in titanium
- The yield of elastically scattered 17 to 21 MeV neutrons from the reaction C¹² (n,n) C¹²
- Gas flow calculations for fluidized-bed coating of nuclear fuel particles
- Diffusion in body-centered cubic metals zirconium, vanadium, niobium, and tantalum
- Characterization of spheroidal UO₂ particles and studies of fabrication variables for core B fuel plates of the Enrico Fermi fast breeder reactor
- Measurement and shell model interpretation of the low-lying nuclear energy levels of niobium-92
- Effects of hydrogen on the high-temperature flow and fracture characteristics of metals
- Laboratory development of processes for fixation of high-level radioactive wastes in glassy solids :wastes containing (1) aluminum nitrate and (2) the nitrates of the constituents of stainless steel