Browse TRAIL Inventories

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

Decladding of Consolidated Edison Power reactor fuel by Sulfex and Darex processes :cyclic dissolution experiments

Reduction of cupric oxide by hydrogen.

Reduction of cupric oxide by hydrogen.

The catalysis of the hydrogen-oxygen reaction by aqueous slurries of thorium oxide and thorium-uranium oxide

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

Chemical feasibility of homogenous neutron poisons for criticality contols in Consolidated Edison fuel processing solutions

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

Comparison of a fluidized-bed and an agitated-trough chemical reactor for producing ThO₂ from Th(NO₃)₄

Heat transfer, burnout, and pressure drop for water in swirl flow through tubes with internal twisted tapes

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

Tributyl phosphate-hydrocarbon diluent repurification in radiochemical processing at ORNL :status summary

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

Wavelength table of rare-earth elements and associated elements including zirconium, thorium, hafnium, rhenium, and tellurium

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.

Purification of beryllium compounds :a literature survey

Zirflex process for PWR blanket fuel :


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