Search U.S. government technical reports digitized or harvested by TRAIL.
The solubility of nitrogen and oxygen in lithium and methods of lithium purification
An evaluation of solid moderating materials
Catalyzed hydrolysis of pyrophosphate by thorium oxide
A sampling device for molten-salt systems
Reduction of cupric oxide by hydrogen.
Reduction of cupric oxide by hydrogen.
Effect of heat flux on the corrosion of aluminum by water :
The admittance and transfer functions of solid core electromagnets
Calculation of termperature rise in deeply buried radioactive cylinders
Level transducers for liquid metals
Removal of radioiodine from air streams by activated charcoal
A study of graphite-moderated Th-U²³³ breeder systems
Recovery of uranium and thorium from graphite fuels.
The fast multiplication effect of beryllium oxide in reactors
The scattering and polarization of spin one particle
Solubility of zirconium dibutyl phosphate in solvent extraction solutions
Apparatus for determining linear thermal expansions of materials in vacuum or controlled atmosphere
Thorex pilot plant corrosion studies.
Effective cadmium cutoff energies :supplement
Process for dissolution of Borax IV reactor fuel :laboratory development
Maximum volume-to-stress ratio for a two-radii-contour diaphragm pump
Measurement of stopping power of copper by calorimetric methods
Toroid rotator for small-scale dynamic corrosion studies :design, fabrication, and operation
Organic compounds in fission reactors :
Corrosion of materials by lithium at elevated temperatures
Surface temperatures of irradiated ORR fuel elements cooled in stagnant air
Safeguard report on the proposed method of annealing graphite in the X-10 reactor
Purification of Pm¹⁴⁷ from fission-produced reare earths
Design, development, and operation of metal-diaphragm reactor-service pumps
An IBM-704 code for a harmonics method applied to two-region spherical reactors
Fluorox process :production of UF₆ in a fluidized bed reactor
Experimental molten-salt-fueled 30-Mw power reactor
Calibration and testing of 2- and 3¹/₂-in. magnetic flowmeters for high-temperature NaK service
Solids separation by a hydraulic cyclone with a batch underflow receiver
Solubilities of selected metals in mercury :Hermex process
Gas-cooled reactor program quarterly progress report for period ending ...
Controlled pH stripping of uranium from amines
In-pile corrosion test loops for aqueous homogeneous reactor solutions
Effect of plasma potential on DCX steady state
Oak Ridge National Laboratory 1963
Annual progress report civil defense research project.