In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C (open access)

In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment:  Dynamic Utility Test Loop (open access)

Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
System: The UNT Digital Library
Progress Report on Loading of Titanium with Deuterium (open access)

Progress Report on Loading of Titanium with Deuterium

Report issued by the University of California Radiation Laboratory discussing an experiment in which a system was designed and built to load titanium with deuterium gas of a high purity. It discusses the results and the parameters affecting the amounts and purity of the absorbed gas.
Date: May 5, 1955
Creator: Ruff, James W.
System: The UNT Digital Library
Decontamination of ORNL Purex Pilot Plant (open access)

Decontamination of ORNL Purex Pilot Plant

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
System: The UNT Digital Library
An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases (open access)

An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.
Date: May 5, 1951
Creator: Mattraw, H. C.
System: The UNT Digital Library