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An Influence Function for the Beta Activity of Uranium(235) Fission Products (open access)

An Influence Function for the Beta Activity of Uranium(235) Fission Products

Abstract: "Computations have been made of the total beta activity of the fission products arising from the slow neutron fission of U-235. A curve is given exhibiting the activity the activity per unit fission, for time intervals after fission ranging from 0.01 second to 10 years. This influence function is compared with some published experimental data and with the statistical curve of Way and Wigner. A curve facilitates estimation of the activity in the particular case where the fission rate has been constant throughout a known time interval. Finally, an influence function for the particular group of fission products consisting of complete and partial chains having volatile first members is given. This report is based on studies conducted for the Atomic Energy Commission under Contract AT-11-1-GEN-8."
Date: September 1, 1950
Creator: Thornton, J. Kendall & Houghton, William J.
Object Type: Report
System: The UNT Digital Library
Radium-Barium Separation Process: Part 2 - Chromate Fractionation Procedures (open access)

Radium-Barium Separation Process: Part 2 - Chromate Fractionation Procedures

Abstract: A comprehensive study was made of various fractionation systems for the fractional separation of barium-radium mixtures. The most efficient and simplest fractionation scheme was chosen on the basis of the thermodynamics of separating the constituents of mixed crystals and of the combining fractions in a system of repeating composition. This scheme was applied to the separation of barium and radium by utilizing the countercurrent batch fractionation of the chromates. The chromate procedure was evaluated by a comparison with the classic methods which employ the fractional crystallization of the halides. The chromate method is more practical on the basis of radium enrichment per fractionation step, control of precipitating conditions, simplicity, and speed of operation.
Date: April 1, 1951
Creator: Salutsky, Murrell Leon; Stites, J. G. & Joy, E. F.
Object Type: Report
System: The UNT Digital Library
Determination of half life of polonium-210 by counting: final report (open access)

Determination of half life of polonium-210 by counting: final report

Introduction: "A number of determination have been made of the half life of polonium-210 by calorimetry. Counting affords an entirely different method of determining half lives and requires only a small amount of activity. Therefore for comparison a half-life determination by counting was undertaken with a sample of approximately 0.5 millicurie of polonium."
Date: June 1, 1951
Creator: Curtis, Mary Lou
Object Type: Report
System: The UNT Digital Library
Processing Tests in Granular Resistance Furnaces for Preparing High Purity Graphite (open access)

Processing Tests in Granular Resistance Furnaces for Preparing High Purity Graphite

Report discussing two trial runs for a grannular resistance processing furnace, in which the goal was to produce high purity graphite. These tests were a continuation of a series of trial runs that had previously yielded inconsistent results.
Date: March 1, 1948
Creator: Sermon, G. T.
Object Type: Report
System: The UNT Digital Library
Radioactivity Dissemination Near Uranium Processing Mills (open access)

Radioactivity Dissemination Near Uranium Processing Mills

This report follows a preliminary survey made to study radioactive contamination of the soil (and to some extent in the air and waters) in the vicinity of seven uranium processing mills.
Date: April 1, 1961
Creator: Feldman, M. H.; Troianello, Emilio J.; Coates, G. K. & Sheehan, W. R.
Object Type: Report
System: The UNT Digital Library
The Preparation of Uranyl Carbonate and Measurement of Its Solubility (open access)

The Preparation of Uranyl Carbonate and Measurement of Its Solubility

From summary: "A method for the preparation of normal uranyl carbonate has been developed. Heretofore, this compound has been known only as a rare, naturally occurring material." The report further discusses the physical properties of the compound, its solubility in water, and its interaction with sodium carbonate.
Date: August 1, 1949
Creator: Miller, P. D.; Pray, H. A. & Munger, H. P.
Object Type: Report
System: The UNT Digital Library
Physical Constants of Uranium Tetrachloride (open access)

Physical Constants of Uranium Tetrachloride

Abstract: Exceedingly pure uranium tetrachloride was prepared for use in determining the physical constants of the compound. Measurements were obtained of the melting point and boiling point at pressures ranging from the triple point pressure to atmospheric pressure. Calculations were made of the vapor pressure equation for the liquid, the heat of evaporation, molar boiling point elevation, the vapor pressure equation for the solid, and the critical temperature.
Date: April 1, 1947
Creator: Young, H. S. & Grady, H. F.
Object Type: Report
System: The UNT Digital Library
The Uranium-Cobalt System (open access)

The Uranium-Cobalt System

Abstract: "A phase diagram for the uranium-cobalt system has been constructed, based on thermal, microscopic, X-ray and chemical data. The results indicate the existence of three compounds and two eutectics, one of which shows a lowering of the melting point of uranium by approximately 400 C."
Date: March 1, 1946
Creator: Noyce, William Knight & Daane, A. H.
Object Type: Report
System: The UNT Digital Library
Properties of Tin Oxide: Base Ceramics (open access)

Properties of Tin Oxide: Base Ceramics

From summary: "Various thermal and mechanical properties were measured for sintered tin oxide-matrix compacts which nominally were composed of 99 per cent by weight of tin oxide, SnO2, and one per cent by weight of zinc oxide ZnO...The tin oxide body might be expected to give good service under conditions of severe thermal shock and in an oxidizing atmosphere at temperatures up to 1500°F."
Date: August 1, 1951
Creator: Quirk, John F. & Herman, C. G.
Object Type: Report
System: The UNT Digital Library
Ozonosphere Observations from Propagation of Atomic Blast Waves (open access)

Ozonosphere Observations from Propagation of Atomic Blast Waves

Abstract: "Observations of refracted sound waves from atomic tests at the Nevada and Pacific Proving Grounds are evaluated to show temperature and winds in the ozonosphere. A simplified method of making these interpretations is presented to reduce the computation work load normally associated with atmospheric sound studies."
Date: October 1, 1954
Creator: Reed, Jack W.
Object Type: Report
System: The UNT Digital Library
Recalculation of Critical Masses of U and Pu Water Tamped Solutions (open access)

Recalculation of Critical Masses of U and Pu Water Tamped Solutions

A report discussing a method of computing the critical mass of U₂₃₅ contained in a water solution confined to a spherical core and surrounded by an infinite water tamper, a modification of said method in which the effect of the resonance fission and absorption is taken into account, and physical constants required to calculate the critical mass using these methods.
Date: September 1, 1949
Creator: Greuling, Eugene
Object Type: Report
System: The UNT Digital Library
Summary Report for April, May and June, 1951 (open access)

Summary Report for April, May and June, 1951

Report discussing progress made by the Chemistry Division (Section C-1) of the Argonne National Laboratory for the months of April, May and June, 1951. Information is divided into "Nuclear Chemistry and Radiochemistry" and "Basic Chemistry".
Date: August 1, 1951
Creator: Manning, W. M. & Osborne, D. W.
Object Type: Report
System: The UNT Digital Library
Oak Ridge Static Autoclave Water Decomposition Test (open access)

Oak Ridge Static Autoclave Water Decomposition Test

Abstract: "Steady states decomposition product partial pressures of water exposed to an epithermal neutron flux of about 2 x 10-11, at 235F, were 0.4 to 0.65 psi. Recombination studies were made by adding hydrogen and oxygen gases to water under irradiation at different temperature and flux levels. The data show a significant effect of temperature on the rate of pressure drop of the added hydrogen and oxygen. In operating at two flux levels, 1.2 x 10-11 and 2.0 x 10-11, no difference in the rate of pressure drop with flux could be detected with the instrumentation on the test apparatus."
Date: May 1, 1951
Creator: Humphreys, J. R., Jr.; Abers, E. L. & Brown, P. E.
Object Type: Report
System: The UNT Digital Library
Semi-Annual Progress Report in Metallurgy for the Period October 1, 1950 - March 31, 1951 (open access)

Semi-Annual Progress Report in Metallurgy for the Period October 1, 1950 - March 31, 1951

Report discussing progress made in metallurgy by the Ames Laboratory during the the term from October 1, 1950 to March 31, 1951.
Date: May 1, 1951
Creator: Wilhelm, Harley A.
Object Type: Report
System: The UNT Digital Library
Semi-Annual Progress Report in Chemistry for the Period October 1,1950--March 31,1951 (open access)

Semi-Annual Progress Report in Chemistry for the Period October 1,1950--March 31,1951

Report discussing the progress made on various chemistry research projects at Ames Laboratory during the period from October 1, 1950 to March 31, 1951.
Date: May 1, 1951
Creator: Ames Laboratory
Object Type: Report
System: The UNT Digital Library
The Preparation of Uranium Foil (open access)

The Preparation of Uranium Foil

"Uranium foil 0.001 inch thick was made by rolling cast specimens at 600°C in a steel jacket and cold rolling the resulting 0.012-inch-thick strip to the desired thickness. The foil was of excellent quality, having no pin holes and only very slight cracking."
Date: October 1, 1948
Creator: Saller, Henry A. & Keeler, J. R.
Object Type: Report
System: The UNT Digital Library
Electrodecontamination of Stainless Steel (open access)

Electrodecontamination of Stainless Steel

Abstract: "In experimental studies, decontamination factors of 1000 to 3000 were obtained by electrostripping deposited radioactivity from stainless steel surfaces, used as the anode, in 2% sulfuric acid at current densities as low as 0.01 amp/in.-2. Stainless steel cathodes were used. The method was successfully applied to contaminated equipment."
Date: November 1, 1954
Creator: Bennett, M. R.
Object Type: Report
System: The UNT Digital Library
A Study of the Carrier Distillation Excitation of Iron in U3O8 (open access)

A Study of the Carrier Distillation Excitation of Iron in U3O8

Abstract: "A radioactive tracer, Fe^59, was used to determine the disposition of iron as a result of the excitation of a U3O8 matrix in a d - c arc. Two different spectrographic procedures, both using carrier distillation excitation techniques, were compared as to the percent of iron volatilized, the percent of iron diffused into the electrode and the percent of iron remaining in the residual charge."
Date: October 1, 1957
Creator: Atwell, M. G. & Pepper, C. E.
Object Type: Report
System: The UNT Digital Library
Results of Experiment 1: FCE Calibration With BORAX Core (open access)

Results of Experiment 1: FCE Calibration With BORAX Core

Summary: The justification of using polyethylene whose hydrogen density of 0.132 gm/cm³ with a distributed void of 15.9 percent as a mockup of water at 70°F and having a hydrogen density of 0.111 gm/cm³ was tested in the FCE. A mockup close to the BORAX core was built and its critical mass determined. Corrections were calculated for differences in the hydrogen desnity and self shielding of the fuel. The effective FCE critical mass agreed with that of the BORAX core to within one percent.
Date: October 1, 1956
Creator: Starr, E. & Toops, Edward Chassell
Object Type: Report
System: The UNT Digital Library
Purification of Uranium Tetrachloride by Fractional Condensation (open access)

Purification of Uranium Tetrachloride by Fractional Condensation

"The effect of a single vacuum sublimation of contaminated uranium tetrachloride, with fractional condensation of the vapors, was investigated to determine whether a high degree of purity would result. It was found that this procedure was an excellent and simple method for obtaining exceedingly pure uranium tetrachloride."
Date: April 1, 1947
Creator: Young, H. S. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
A Spherical, Single Space Variable, Three-Region, Multigroup Reactor Calculation on IBM-701. (Program D) (open access)

A Spherical, Single Space Variable, Three-Region, Multigroup Reactor Calculation on IBM-701. (Program D)

Report describing "Program D", a nuclear reactor calculation program for the AGT Evendale IBM 701 digital computer. Explanatin of necessary input data and the machine output is included.
Date: April 1, 1955
Creator: Nix, E. D.
Object Type: Report
System: The UNT Digital Library
Reactivity of Dibutyl Carbitol (open access)

Reactivity of Dibutyl Carbitol

Report discussing experiments to determine if the tri-ether (referred to in the report as dibutyl carbitol or carbitol) "was susceptible of a high degree of reactivity when used as an extraction agent for the removal of uranium from aqueous solutions."
Date: April 1, 1947
Creator: Susano, C. D.
Object Type: Report
System: The UNT Digital Library
Process Monitor Analysis Victoreen Model 350 (open access)

Process Monitor Analysis Victoreen Model 350

Abstract: An analysis of the improved Model Number 350 Process Monitor was made so that it could be determined if this instrument would fulfill the need for gamma radiation detection instruments in the production buildings of Y-12. The results of these tests indicated the possibility of marked improvement in the monitor characteristics with minor redesigns. After these improvements have been made, this instrument will be a satisfactory monitor for this area.
Date: May 1, 1947
Creator: Harter, J. A. & Olson, E. L.
Object Type: Report
System: The UNT Digital Library
Mound Laboratory Liquid Waste Disposal Research Quarterly Report for April - June, 1950 (open access)

Mound Laboratory Liquid Waste Disposal Research Quarterly Report for April - June, 1950

The following report is a quarterly report conducted by the Monsanto Chemical Company for liquid waste disposal research, covering the period April through June, 1950. This report discusses experiments that were carried out with both neutralized second-cycle wastes and pure isotope which show that, in general, the presence of fluoride ion does not interfere with the removal of fission products from waste solutions.
Date: July 1, 1950
Creator: Monsanto Chemical Company
Object Type: Report
System: The UNT Digital Library