TRAIL - Technical Report Archive and Image Library

A summary of the separation operations

Chemistry associated with the electromagnetic separation of chromium isotopes

Boundary values for the inner radius of a cylindrical annular reactor

On Kofink's approximate solution of the neutron transport equation

High temperature pressure transmitter evaluation

Solubility relations among some fission product fluorides in NaF-ZrF₄-UF₄ (50-46-4 mole %)

Oxidation of uranium tetrafluoride in a moving-bed reactor

The recrystallization and grain growth of Inconel

Laboratory studies on the ground disposal of ORNL intermediate-level liquid radioactive wastes

Thorex process :third uranium cycle studies

Safeguard report for a stainless steel research reactor for the BSF (BSR-II)

Development of the Excer process.

Gamma-ray dose rates resulting from neutron captures in air

Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements

The ORNL thermonuclear program

A modification of the spherical harmonics method in neutron transport theory

Bremsstrahlung spectra in NaI and air

Radiation excursions at the ORNL critical experiments laboratory.

Some aspects of the recovery of lithium from spodumene

Preparation and metallography of arc-melted uranium carbides

Thermometric (enthalpymetric) titration of free acid in the presence of certain hydrolyzable ions

Development of the Excer process.

Development of a continuous ion exchange process for the removal and recovery of high-purity cesium from alkaline waste

Preparation of metallographic specimens through vibratory polishing

The use of tri-n-octylphosphine oxide in the solvent extraction of zirconium

Comparison of pool-type reactor critical experiments with two-group and thirty-group calculations

An evaluation of asphalt and other materials for lining radiochemical waste storage basins

Preparation of ThO₂ for homogenous reactor blanket use

The ORNL gas-cooled reactor :advanced concepts

Separation of fluoride from refractory materials by fusion-pyrolysis

Triple correlations

Dissolution of sintered thorium-uranium oxide fuel in nitric acid-fluoride solutions

Final report :development and testing of air-melted nickel-molybdenum alloys with minor alloying additions

Measurement of electron flux media bombarded by x-rays

Comparison of theoretical and experimental filtered x-ray spectra

Solubility and stability of PuF₃ in fused alkali fluoride-beryllium fluoride mixtures

Gas-cooled reactor project semiannual progress report for period ending ...

Reactor safety system response

Articles published in technical journals, reports published, papers presented at scientific meetins, and inventions disclosed during 1957 or ORNL staff members.

Attenuation in Water of Radiation from the Bulk Shielding Reactor: Measurements of the Gamma-Ray Dose Rate, Fast Neutron Dose Rate, and Thermal-Neutron Flux

Health Physics Division Annual Progress Report, July 31, 1958

Homogeneous Reactor Project Quarterly Progress Report: November 1957-January 1958

Neutron Physics Division Annual Progress Report, September 1, 1958

The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 1: Summary Report

The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 2: Plant Design

The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 3: Plant Design

The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 4: Plant Design

Experimental Evaluation of the Radiation Protection Afforded By Residential Structures Against Distributed Sources

Applied health physics and safety annual report.

A study of cavity ionization as a function of atomic number by use of a miniature counter

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