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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
System: The UNT Digital Library
Dry Fluoride Process Status Report (open access)

Dry Fluoride Process Status Report

Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [From Abstract, Summary]
Date: March 27, 1951
Creator: Leuse, R. E.
System: The UNT Digital Library
Analytical Chemistry Division Semiannual Progress Report For Period Ending October 20, 1955 (open access)

Analytical Chemistry Division Semiannual Progress Report For Period Ending October 20, 1955

The development of ionic methods for the determination of corrosive products in the highly radioactive Homogeneous Reactor (HR) fuels has been of major interest in the work of the Ionic Analyses Laboratory. Methods for the spectrophotometric determination of aluminum and for the polarographic determination of iron in HR fuels have been developed. The polarographic determination of molybdenum in uranyl sulfate solutions was studied. A polarographic method for the determination of zinc was developed. A fluorometric method for the determination of microgram amounts of fluoride was studied. Three organic reagents were investigated as precipitants for microgram quantities of zirconium in HR fuel. The automatic photometric titration technique was applied to the determination of thorium and of sulfate. A method was developed for the ion-exchange separation and potentiometric titration of cobalt. The ultraviolet absorption spectra of technetium and rhenium were studied.
Date: December 27, 1955
Creator: Kelley, M. T.; Susana, C. D. & Rooen, H. P.
System: The UNT Digital Library
The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion (open access)

The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion

Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]
Date: March 27, 1951
Creator: Olsen, Arnold R.
System: The UNT Digital Library
Fall-Out in Southeastern United States During January and February 1951 from the Nevada Atomic Tests (open access)

Fall-Out in Southeastern United States During January and February 1951 from the Nevada Atomic Tests

Air filter and rainwater collections of atmospheric fall-out were made at Atlanta, Georgia; Urbana, Illinois; Topeka, Kansas; Fort Worth, Texas; and Nashville, Tennessee. Collections reflect the effects of the radioactive cloud from the Nevada tests.
Date: November 27, 1951
Creator: Davis, F. J.
System: The UNT Digital Library
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961 (open access)

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: June 27, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
HRP Radiation Corrosion Studies: In-Pile Loop L-4-11 (open access)

HRP Radiation Corrosion Studies: In-Pile Loop L-4-11

Report issued by the Oak Ridge National Laboratory discussing radiation corrosion studies. As stated in the introduction, "the purpose of this experiment was to compare the performance of a large number of materials under similar irradiation and exposure conditions" (p. 1). This report includes tables, illustrations, and photographs.
Date: June 27, 1958
Creator: McWherter, J. R. & Baker, J. E.
System: The UNT Digital Library
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process (open access)

Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Date: May 27, 1963
Creator: Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
System: The UNT Digital Library
Products Produced in Batch Neutron Irradiation of Thorium (open access)

Products Produced in Batch Neutron Irradiation of Thorium

Calculated data and graphs describing the effects of batch thermal-neutron irradiation of thorium, the usual method of operation of heterogeneous reactors, are presented. The buildup and decay of U233, Pa233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of these irradiation products on the Thorex chemical separation process are indicated briefly.
Date: December 27, 1955
Creator: Gresky, A. T. & Arnold, E. D.
System: The UNT Digital Library