The Conversion of UF4 to U3Os (open access)

The Conversion of UF4 to U3Os

Methods of conversion of UF4 to U3O8 by fusion with ammonium oxalate dihydrate and other salts are described.
Date: May 28, 1941
Creator: Tevebaugh, A. D.; Tevebaugh, R. D.; Cline, W. D. & Warf, James C.
Object Type: Report
System: The UNT Digital Library
Capture Cross Section of Si for Thermal Neutrons (open access)

Capture Cross Section of Si for Thermal Neutrons

The following report analyzes different values and measurements that give the same results for the captured cross section of thermal neutrons for Si.
Date: May 6, 1942
Creator: Coon, J. H.
Object Type: Report
System: The UNT Digital Library
Radiation Chemistry: The Chemical Effects of Radiation on Matter (open access)

Radiation Chemistry: The Chemical Effects of Radiation on Matter

Lecture notes from a training program. "It is the function of the section on radiation chemistry to determine the effects of all radiations and high energy particles produced under the various operating conditions on all the materials which will be exposed to them."
Date: May 3, 1943
Creator: Burton, Milton
Object Type: Report
System: The UNT Digital Library
The Effect of Fast Fission on k (open access)

The Effect of Fast Fission on k

The importance of fast neutron fission (i.e., fission caused by neutrons before being slowed down) was recognized by Szilard, and calculations similar to the present one have already been carried out by him, Feld, Ashkin, Wheeler, Wigner and others. The purpose of the present paper is to give a general formula for the contribution of fast fission to the multiplication constant, which will include all the cases already considered and will be applicable to more complicated geometries than those considered by the previous writers.
Date: May 4, 1943
Creator: Castle, H.; Ibser, H.; Sacher, G. & Weinberg, Alvin Martin, 1915-2006
Object Type: Report
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943

Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from several organic materials including those suggested by the physiological shield have been extended to include both beta and deuteron bombardments. Samples of "Press-wood" are being evaluated. The effect of current on the H2O2 production in water containing I- has been studied at several I- concentrations. Water contain-dissolved CO2 shows the presence of oxidant (presumably H2O2). H2O2 has been produced by recoil protons from the scattering of fast neutrons in de-oxygenated water. Radioactive solutions do not greatly affect the applicability the glass electrode providing the electrode is thoroughly washed with distilled water before immersion in the standard buffer solution.
Date: May 15, 1943
Creator: Franck, J.
Object Type: Report
System: The UNT Digital Library
On the Multiplication Constant of Homogeneous Mixtures of U with Various Moderators (open access)

On the Multiplication Constant of Homogeneous Mixtures of U with Various Moderators

The following represents a summary of calculations on the multiplication constant of homogeneous mixtures of uranium and different moderators. These calculations were made possible by Fermi's determination of the age of neutrons and by the extrapolation to higher scattering cross-sections of the resonance absorption of uranium as measured by C. Creutz. According to Fermi, the former quantity is 120 sq. cm. The latter is given in the two attached graphs. The first (Fig.1) of these goes as high as a scattering cross-section of 70 x 10-24 cm.2 per uranium atom, and its highest point is taken from a measurement of Cruetz's in which a mixture of U3O8 and graphite was used.
Date: May 16, 1943
Creator: Wigner, Eugene Paul, 1902-1995 & Stephenson, J.
Object Type: Report
System: The UNT Digital Library
The Biologic Effects of Radiation ; Training Program Lecture Notes (open access)

The Biologic Effects of Radiation ; Training Program Lecture Notes

The following report provides data taken from investigations on radiation and the different biologic effects on it.
Date: May 17, 1943
Creator: Cantril, Simeon T.
Object Type: Report
System: The UNT Digital Library
Time Variation of Percent Distribution of Fission Activity in Bombarded Uranyl Nitrate (open access)

Time Variation of Percent Distribution of Fission Activity in Bombarded Uranyl Nitrate

"In this report are presented three figures which show how the relative activities (expressed as percentages of total activity) of the individual fission elements (produced by neutron bombardment of uranyl nitrate) vary with cooling time."
Date: May 19, 1943
Creator: Brady, E. L. & Coryell, Charles D.
Object Type: Report
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Heavy Water, Report for the Month Ending May 1, 1944 (open access)

Metallurgical Laboratory, Chemical Research - Heavy Water, Report for the Month Ending May 1, 1944

Technical report with short reports on (1) Heavy water analysis and standardization, and Specific gravity of pure D2O; (2) Homogenous exponential experiment; (3) Recombination of pile gases; (4) Slurry pumping studies; and (5) Electron microscope laboratory.
Date: May 16, 1944
Creator: Hogness, T. R. (Thorfin Rusten), 1894-; Hiskey, C. F. & Eidinoff, Maxwell Leigh, 1915-
Object Type: Report
System: The UNT Digital Library
Preparation of U233 (open access)

Preparation of U233

Technical report. The object of the research is to determine the procedure and equipment for the preparation of U233 on a semi-works scale. The general proposed procedure is that thorium carbonate in aluminum cans will be irradiated with pile neutrons. The Pa233 resulting from neutron absorption the Th232 and the decay of Th233 will be extraction from 99% of the thorium and the natural U in thorium by MnO2 precipitations. The Pa233 will then be allowed to decay to U233 which in turn will be isolated from the remaining Th and partially decayed Pa233 by ether extraction.
Date: May 16, 1944
Creator: Apple, R. S.
Object Type: Report
System: The UNT Digital Library
Thermal Stresses Arising from Defective Strip in Bond (open access)

Thermal Stresses Arising from Defective Strip in Bond

Stresses set up by an insulating strip in the bond are estimated and found to be small compared to those normally present without the defect.
Date: May 18, 1944
Creator: Young, G.
Object Type: Report
System: The UNT Digital Library
A Case of Rod Warping (open access)

A Case of Rod Warping

Warping of a rod by a variation in heat transfer coefficient around the periphery is considered. Estimates for some simple cases are given, and a more precise numerical calculation is carried out in ne instance.
Date: May 27, 1944
Creator: Murray, F. & Young, Gale Jay
Object Type: Report
System: The UNT Digital Library
The Diffusion Length of Thermal Neutrons in Uranium (open access)

The Diffusion Length of Thermal Neutrons in Uranium

Measurements made in a uranium cylinder result in a mean value of 1.55 cm. for the diffusion length L for distances of 1 to 4 cm. from the base of the cylinder. Calculations give a value which agrees with the experimental result and show further that L increases from 1.40 to 1.63 cm. as the neutrons diffuse a distance of 5 cm. into the uranium.
Date: May 27, 1944
Creator: Hughes, Donald James, 1915-1960 & Bragdon, E. W.
Object Type: Report
System: The UNT Digital Library
Determination on Neutron Density With Bismuth Foils : Final Report - Problem Assignment 131 - X21P (open access)

Determination on Neutron Density With Bismuth Foils : Final Report - Problem Assignment 131 - X21P

It is usual to determine the density of neutrons by using foils of metals which become radioactive as a result of bombardment in the region under investigation. From the rate of disintegration of the newly formed radioactive element the number of neutrons absorbed can be calculated. By use of the capture cross section of the element of which the foil is composed the density of the neutrons can then be computed. By counting the alpha particles from a bismuth foil of known weight after exposure to neutrons the density of the neutrons which produced this activity can be calculated. The least accurately known value which enters into this evaluation is the capture cross-section of bismuth for pile neutrons. This value may be improved by future measurements. It is of importance only for absolute measurements of neutron density so that relative values can be measured with considerable accuracy on the basis of known data.
Date: May 30, 1944
Creator: Curtiss, Leon Francis, 1895-
Object Type: Report
System: The UNT Digital Library
Analysis for Oxide in Thorium Metal (open access)

Analysis for Oxide in Thorium Metal

Abstract. to estimate the oxygen picked up by thorium in casting a rapid method of running the acid insoluble content was developed. the quickest procedure consists of reacting with mixed acids, fuming with perchloric and filtration to separate the "free" thorium from the "combined". The precipitate is ignited and weighed as thorium dioxide.
Date: May 12, 1945
Creator: Ayers, A. S.
Object Type: Report
System: The UNT Digital Library
Stabilizer for Temperature Control Equipment (open access)

Stabilizer for Temperature Control Equipment

From abstract: "A simple electronic circuit is described, the use of which greatly improves the temperature regulations obtainable with Beta equipment. The circuit utilizes the time derivative of the temperature to counteract oscillation and overshoot. No other changes are required in existing equipment for installation of the stabilizer."
Date: May 14, 1945
Creator: Macleish, K. G. & Palmer, R. C.
Object Type: Report
System: The UNT Digital Library
Analysis of Heavy Water by Equilibration (open access)

Analysis of Heavy Water by Equilibration

Technical report discussing that the deuterium concentration of heavy water can be determined by equilibrating the water with deuterium gas in the presence of a catalyst with subsequent analysis of the equilibrated gas on the mas spectrometer. The apparatus for equilibration analyses maybe be considered in three parts: 1) apparatus for introducing the ingredients into the reaction chambers; 2) the reaction chambers; 3) the mass spectrometer for analysis of the equilibrated gas. The isotopic composition of the deuterium gas to be used as the starting material is primarily governed by what gases are available. In general it is best to use gas within about one percent on either side of the final equilibrium composition. No reaction takes place between deuterium gas and water molecules in the absence of a catalyst. Platinum oxide is used as the catalyst.
Date: May 15, 1945
Creator: Fischer, R. B.; Potter, R. A. & Voskuyl, R. J.
Object Type: Report
System: The UNT Digital Library
The Extraction of Uranium into Hexone as Uranyl Thiocyanate from Thorium Nitrate Solutions (open access)

The Extraction of Uranium into Hexone as Uranyl Thiocyanate from Thorium Nitrate Solutions

Technical report with six sections describing the process: (1) The reaction of HN)3 with HSCN; (2) The distribution of nitric acid between hexone and water; (3) The distribution of HSCN between hexone and water; (4) The solubility of thorium sulfate in various extraction solutions; (5) The distribution of protoactinium and fission elements between hexone and aqueous thiocyanate solutions; and (6) Separation of uranium from thorium by extraction into hexone as UO2(SCH)a.
Date: May 18, 1945
Creator: Reas, William H.
Object Type: Report
System: The UNT Digital Library
Development of Equipment for the Purification of Mercury by Distillation (open access)

Development of Equipment for the Purification of Mercury by Distillation

Abstract: "An investigation of the mercury salvage program has resulted in the development of an improved high compacity type of distillation apparatus. The still, electrically heated and essentially automatic in its operation, will produce at a rate greater than 75 pounds per hour and develop a product 99.99% pure or better. This still will handle the lowest grade crude of amalgam that can pass through the feed lines and will continue to develop a pure prodcut for comparatively long periods of time. The clean-out operation is amazingly simple and convenient and may be done within one-half hour while the apparatus itself is still hot. Two models of this design are scheduled for installation in a mercury recovery room of the Alpha Analytical Department of Building No. 9207."
Date: May 26, 1945
Creator: Lee, J. E. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
Progress Report on Corrosion Tests in TCl₄ (open access)

Progress Report on Corrosion Tests in TCl₄

This report describes progress in testing the corrosion resistance of alloys of TCl₄. The steps and conditions of the testing procedures are given as well as conclusions and photos of TCl₄.
Date: May 26, 1945
Creator: Mash, Donald R.
Object Type: Report
System: The UNT Digital Library
Metallurgical Laboratory, Physics Section, Report for the Month Ending May 31, 1945 (open access)

Metallurgical Laboratory, Physics Section, Report for the Month Ending May 31, 1945

Technical report with short reports from the (1) Physics Section I; (2) Physics Section II ; and (3) Physics Section III.
Date: May 31, 1945
Creator: Snell, A. H.; Nordheim, L. W. & Wollan, Ernest Omar
Object Type: Report
System: The UNT Digital Library
The Beta-Gamma Hand and Foot Counters (open access)

The Beta-Gamma Hand and Foot Counters

Abstract: This is basically a counting rate meter, with an alarm circuit, operating from four GM tubes as the detecting elements. The Hand Counter comprises four logarithmic counting rate meters working from four GM tubes mounted individually, with associated electronic circuits, in suitable shields with a metal mesh type of window. Both sides of both hands are sampled simultaneously. In the Foot Counter, two GM tubes are separately and mounted in a suitable mesh window shielded with the electronic circuit; the foot counter uses only two counting rate meters, and both feet are sampled simultaneously. Each circuit is built in two parts; two tubes are in the shield and the balance of the circuit is in the electronic unit which is a standard 17" x 13" chassis. Circuit diagrams are included.
Date: May 1946
Creator: Bradley, W. H.
Object Type: Report
System: The UNT Digital Library
The Coprecipitation of Thorium and Uranium Peroxides (open access)

The Coprecipitation of Thorium and Uranium Peroxides

From abstract: "Experiments covering the coprecipitation of Thorium and Uranium peroxides are described on synthetic and actual 1300 cycle machine wash effluents."
Date: May 10, 1946
Creator: Oringer, Roy; Woodard, R. W. & Larson, C. E.
Object Type: Report
System: The UNT Digital Library
The Deposition of Plutonium and Certain Fission Products in Bone as a Decontamination Problem (open access)

The Deposition of Plutonium and Certain Fission Products in Bone as a Decontamination Problem

The following report discusses the deposition of radioactive elements during a nuclear fission in the skeleton. Studies are concerned with chronic effects of toxic radiation developing within the bone marrow and decontaminating the cells.
Date: May 15, 1946
Creator: Copp, D. Harold; Greenberg, David M. & Hamilton, Joseph G.
Object Type: Report
System: The UNT Digital Library