TRAIL - Technical Report Archive and Image Library

Investigation of spectrochemical solution-methods of analysis :the use of designed experiments and statistical methods of analysis in the interpretation of data

Controlled potential coulometric titration of plutonium :application to PRFR samples

Adsorption of xenon and argon on graphite

Recovery of uranium from DI (2-ethylhexyl) phosphoric acid (dapex) extractant with ammonium carbonate

Metallurgy of zircaloy-2 :

Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel :laboratory development

Inline instrumentation :gamma monitor, uranium coloimeter

Nuclear data processing on an IBM-704 computer with the Condac program

Development of an electrolytic cell for removal of nickel from HRT fuel solutions

Fused salt fuel processing in the ORNL volatility pilot plant

Purification of promethium by liquid-liquid extraction

Modified zirflex process for dissolution of 1-10% U-Zr alloy fuels in aqueous NH₄F-NH₄NO₃-H₂O₂ :laboratory development

Processing of high-fired uranium dioxide fuels by a reduction - mercury extraction - oxidation process

Mathematics Panel progress report :for period ending September 1, 1958 to December 31, 1959

Some properties of infinite, lumped solenoids

Getting multichannel analyzer data in and out of the IBM-7090 for processing

Manganese bath measurements of [Eta] of U²³³ and U²³⁵

Effect of temperature on radiator weight for space vehicle power plants

Procedure for testing reactor controls pulse amplifier and preamplifier

The lid tank shielding facility at Oak Ridge National Laboratory.

Focusing properties of inhomogeneous magnetic sector fields

Sample scattering corrections in neutron beam experiments

Oak Ridge National Laboratory sampler for the tamalpais underground nuclear detonation experiment

Kinetic equations for plasma and radiation

Thermodynamic properties of the uranium mercurides

Electromagnetic production of pion pairs

A paramagnetic resonance study of hyperfine interactions in single crystals containing [Alpha], [Alpha]-diphenyl-[Beta]- picrylhydrazyl

Measurement of electron attachment in oxygen-methane and oxygen carbon-dioxide mixtures

The feasibility of an unattended nuclear power plant

Viewing equipment for use in the HRT core and blanket vessels

Burnout heat fluxes for low-pressure water in natural circulation

Chemistry of the intercycle evaporator incident of November 20, 1959

Waste disposal in salt.

HFIR preliminary physics report

Slurry feed-pump development

Nonnuclear uses for depleted uranium

Milne problem with capture

Coulometric determination of uranium in power-reactor-fuel-dissolver solutions

Three-minute irradiation at variable power density of prototype CETR fuel pellets

Preparation of americium dioxide by thermal decomposition of americium oxalate in air

Group-theoretical treatment of time- and energy-dependent multiple scattering, with aplication to the slowing-down of neutrons

Corrosion resistance of various ceramics and cermets to liquid metals

Operational safety of the ORNL graphite reactor using enriched-uranium fuel

Fused salt heat transfer.

Relaxation characteristics of Inconel at elevated temperatures

Standard operating procedure for the pool critical assembly

Radiation transmission through boral and similar heterogenous materials consisting of randomly distributed absorbing chunks

Dissociation of H₂⁺ by hydrogen

Equipoise :an IBM-704 code for the solution of two-group, two-dimensional, neutron diffusion equations in cylindrical geometry

Low-temperature thermoluminescence of the gamma-irradiated amino acids and proteins

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