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- Transuranium quarterly progress report for period ending ...
- Fuel cycle development :semiannual progress report for period ending ...
- Calculations of shielding for burned-out reactor fuel elements
- The buildup of heavy isotopes during thermal neutron irradiation of uranium reactor fuels
- Army package power reactor critical experiment
- Operation of the ORNL graphite reactor and of the low-intensity test reactor and preoperation activities at the research reactor annual report for 1956
- Specifications for Army Package Power Reactor (APPR-1) fuel and control rod components
- Fuel costs in spherical slurry reactors
- Investigation of the factors affecting sensitization of army package power reactor (APPR-1) fuel elements
- Fuel costs in single-region homogeneous power reactors
- Components of the fused-salt and sodium circuits of the aircraft reactor experiment
- Solubility relations among some fission product fluorides in NaF-ZrF₄-UF₄ (50-46-4 mole %)
- Radiation excursions at the ORNL critical experiments laboratory.
- Preparation and metallography of arc-melted uranium carbides
- Solubility and stability of PuF₃ in fused alkali fluoride-beryllium fluoride mixtures
- Design of chemical processing plant for homogenous reactor test
- Laboratory development of the sulfex process for the dissolution of consolidated Edison power reactor fuel
- Modified zirflex process for dissolution of zirconium-and niobium-bearing nuclear fuels in aqueous fluoride solutions :laboratory development
- Experiments on the release of fission products from molten reactor fuels
- Fluorox process :production of UF₆ in a fluidized bed reactor
- Solids separation by a hydraulic cyclone with a batch underflow receiver
- Processing of high-fired uranium dioxide fuels by a reduction - mercury extraction - oxidation process
- Development of nondestructive tests for the experimental gas-cooled reactor fuel element
- A study of dissolution of reactor fuels containing zirconium in a titanium vessel
- A study of fission product transport mechanisms in high temperature gas-cooled reactor fuel elements
- Zircex and modified zirflex processes for dissolution of 8% U-91% Zr-1% H TRIGA reactor fuel
- The chemistry of niobium in processing of nuclear fuels
- Instrument for determining crushing strength of particles
- Hot-cell studies of aqueous dissolution processes for irradiated carbide reactor fuels
- Molten-salt solvents for fluoride volatility processing of aluminum-matrix nuclear fuel elements
- Reduction of uranium hexafluoride retention on beds of magnesium fluoride used for removal of technetium hexafluoride
- Chemical development of the 25-TBP process / J.R. Flanary, ... [et. al.].
- Development of nondestructive testing techniques for the high flux isotope reactor fuel element
- Motion of spheres in smooth rotating drums and applications to the coating of nuclear fuel particles