Browse TRAIL Inventories

Fuel cycle development :semiannual progress report for period ending ...

Transuranium quarterly 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

Specifications for Army Package Power Reactor (APPR-1) fuel and control rod components

Operation of the ORNL graphite reactor and of the low-intensity test reactor and preoperation activities at the research reactor annual report for 1956

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


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