Smith County, Texas: Records of wells, drillers' logs, water analyses, and map showing location of wells (open access)

Smith County, Texas: Records of wells, drillers' logs, water analyses, and map showing location of wells

Data complied regarding wells and other water resources, including water quality analysis, measurements, and other relevant information.
Date: September 15, 1937
Creator: United States. Work Projects Administration.
Object Type: Report
System: The Portal to Texas History
Texas Register, Volume 48, Number 37, Pages 5121-5196, September 15, 2023 (open access)

Texas Register, Volume 48, Number 37, Pages 5121-5196, September 15, 2023

A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date: September 15, 2023
Creator: Texas. Secretary of State.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
A Preliminary Study of the Potential to Kinetic Energy Conversion Process in the Stratosphere (open access)

A Preliminary Study of the Potential to Kinetic Energy Conversion Process in the Stratosphere

The potential to kinetic energy conversion process in the lower stratosphere is evaluated using adiabatically derived vertical velocities for the North American region for a five-day period. Preliminary results suggest the possibility that on the average the kinetic energy of stratospheric motions may not result from a conversion of potential energy within the stratosphere. The further implication is that stratospheric motions are mechanically driven by the motions in the adjacent layers of the atmosphere.
Date: September 15, 1959
Creator: White, Robert M., 1923-2015 & Nolan, George F.
Object Type: Report
System: The UNT Digital Library
Pressurized Loop membrane Demineralizer Tests : Final Report [for] January-June 1953 (open access)

Pressurized Loop membrane Demineralizer Tests : Final Report [for] January-June 1953

A membrane demineralizer has been tested in a pressurized loop. The loop water resistivity was maintained in the 1-2 megohm range by ionized solid transfer in the demineralizer. The size and power requirement of the unit tested per gpm flow through the unit, were 2.3 cu ft and 100 watts. In view of the fact that present designed could reduce the size and required maintenance, further studies may be warranted.
Date: September 15, 1954
Creator: Rosenberg, N. W.
Object Type: Report
System: The UNT Digital Library
Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe (open access)

Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe

A mathematical model is presented for the prediction of heat transfer coefficients for fully developed turbulent flow of fluids in circular pipes by analogy to the transfer of momentum. There is also presented an empirical velocity distribution equation derived from existing experimental data for use in the analogy model. Heat transfer coefficients for fluids with Prandtl numbers ranging from 0.01 to 100 and Reynolds numbers ranging from 5x10^3 to 10^7 are presented in tabular and graphical forms for both the case of constant heat flux at the pipe wall and the case of constant temperature at the pipe wall. The heat transfer coefficients computer in this investigation are compared with existing experimental dat, and a discussion of the parameters affecting the heat transfer characteristics of fluids in turbulent motion in circular pipes is presented.
Date: September 15, 1960
Creator: Hefner, R. J.
Object Type: Report
System: The UNT Digital Library
Credit Union Department Newsletter, Number 09-21, September 15, 2021 (open access)

Credit Union Department Newsletter, Number 09-21, September 15, 2021

Newsletter of the Texas Credit Union Department containing departmental news and announcements, deadlines, and other information of importance to credit unions.
Date: September 15, 2021
Creator: Texas. Credit Union Department.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Division of Reactor Development Programs Monthly Report- August 1959 (open access)

Division of Reactor Development Programs Monthly Report- August 1959

Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density versus composition still indicate a drastic reduction in UO2 sinterability with even the slightest additions of PuO2 and a rapid increase with PuO2 contents greater than 20 weight percent. The following table compares densities of pure UO2 and PuO2 after an eight hour soak time:
Date: September 15, 1959
Creator: McEwen, L.H.
Object Type: Report
System: The UNT Digital Library
Interpretation of Westwood, New Jersey Rainfall Data (open access)

Interpretation of Westwood, New Jersey Rainfall Data

"Progress is reported in an evaluation of fission product concentration in rain as a function of time, location, and meteorological setting. Data on rainfall collected at Westwood, N. J., were analyzed for information on the mechanisms of fallout deposition, seasonal variations in fallout, the stratospheric residence time of W/sup 185/ resulting from Operation Hardtack, and the accuracy of pot samplers for sample collection. Data from other collection stations were also analyzed for consistency with Westwood data."
Date: September 15, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Equilibrium Configuration of a Plasma in the Guiding Center Limit (open access)

Equilibrium Configuration of a Plasma in the Guiding Center Limit

"We compute the equilibrium configuration of a collision-free plasma contained in an axially symmetric magnetic field. The plasma is characterized by a non-scalar pressure tensor which is obtained from a microscopic distribution function in a form suggested b the guiding center approximation. The solution is calculated in the limit where the ratio of the width to the length of the plasma region and the ratio of the gas to the magnetic pressure are both small. Boundary values at the midplane as well as the shape of the plasma appear as arbitrary parameters in the solution. We give the solution to a corresponding scalar pressure problem for comparison."
Date: September 15, 1960
Creator: Oppenheim, Alan
Object Type: Report
System: The UNT Digital Library
Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization (open access)

Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization

The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to these techniques will de drawn up to indicate which techniques should be developed further in order that more extensive applications may be found for them.
Date: September 15, 1960
Creator: Isotopes Incorporated
Object Type: Report
System: The UNT Digital Library
Uranium Oxide Slurry Pumping Experiments (open access)

Uranium Oxide Slurry Pumping Experiments

Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating conditions.
Date: September 15, 1944
Creator: Brandt, R. & Dean, G. R.
Object Type: Report
System: The UNT Digital Library
Improved Method for Numerically Solving Multi-Group Reactor Equations (open access)

Improved Method for Numerically Solving Multi-Group Reactor Equations

"A method for solving multi-group reactor equations which arise in the diffusion approximation is outlined. Considerable work has been done on this problem at KAPL and ORNL. Their approach is to replace the differential equations by difference equations. Complications arise in this method where more than one slowing down medium is present since the fluxes are discontinuous at the interfaces. The primary purpose of this article is to develop an exact integral expression for the neutron flux which automatically satisfies the boundary conditions. An iterative method for obtaining the fluxes and critical neutron multiplication ratio based upon the above-mentioned integral expression is given. The only approximation used in obtaining the fluxes, in addition to the use of multi-group diffusion theory as the basic model, is the use of numerical integration to evaluate the analytic expression. The equations for a two region, two group spherical reactor are given in a form suitable for machine programing. The extension to more than two regions is also considered.
Date: September 15, 1954
Creator: Lehman, G. W.
Object Type: Report
System: The UNT Digital Library
The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride (open access)

The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride

"A study has been made of the distribution of tracer fission products and plutonium between small samples of molten uranium and solid uranium oxide, carbine, and nitride. The distribution showed the same behavior i general for all three materials: 1. The rare earth elements, Cs, Ba, and Sr were extracted primarily into the solid scrub phase. 2. Zirconium and Nb partially concentrated in the scrub phase. 3. Plutonium, Mo, and Ru tended to remain completely in the metal phase. The distribution of activities agreed with trends predicted from the thermodynamic data. Uranium oxide appeared to be the most desirable scrub material for removing large amounts of fission products from the uranium while leaving beind the Pu. In addition the uranium metal was not severley contaminated by dissolved oxide."
Date: September 15, 1954
Creator: Keneshea, F. J.; Saul, A. M. & Young, C. Y.
Object Type: Report
System: The UNT Digital Library
A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power (open access)

A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees F. Cost of the complete reactor power plant, consisting of the three reactors, and on 150-megawatt turbogenerator, is estimated to be approximately $43,165,000."
Date: September 15, 1954
Creator: Weisner, Edward F.
Object Type: Report
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953 (open access)

Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs (including the Power Breeder Reactor (PBR) and the Central Station Water Reactor (CSWR)), designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: September 15, 1953
Creator: Argonne National Laboratory. Reactor Enginneering Division.
Object Type: Report
System: The UNT Digital Library
Preferred Orientation in 300 C Rolled and in Recrystallized Uranium Sheet (open access)

Preferred Orientation in 300 C Rolled and in Recrystallized Uranium Sheet

The rolling and recrystallization textures in 300 C rolled uranium sheet were investigated using a Geiger counter diffractometer with the modified Schulz reflection technique. Seven sections of sheet material were used in order to obtain sufficient data for quantitative pole figures by the reflection technique. A special integrating specimen table was used for obtaining and recording the data atomically.
Date: September 15, 1953
Creator: Mueller, Melvin Henry, 1918-; Knott, Harold W. & Beck, Paul A. (Paul Adams), 1908-
Object Type: Report
System: The UNT Digital Library
On the Conductivity of ionized Gas (open access)

On the Conductivity of ionized Gas

The conductivity of ionized gases is treated by a method similar to that used by Alfven in his book "Cosmical Electrodynamics". The results differ from those of Alfven. In particular, it is shown that Alfven's conclusion, that whenever the Hall current disappears the conductivity becomes independent of the magnetic field, is not true in general. Moreover, it is not true under just the conditions of interest for the "Pinch Effect". The main conclusions of the present paper are (1) of currents down a tube, the ion component is the small fraction of m/M of the electron current, regardless of the magnitude of the magnetic field; (2) the conduction along the tube depends on the transverse motion of neutral mass, i.e. on the radial velocity of u(r) of the gas in the tube.
Date: September 15, 1954
Creator: Konopinski, Emil Jan, 1911-
Object Type: Report
System: The UNT Digital Library
Determination of Bismuth in Plutonium-Bismuth Solutions (open access)

Determination of Bismuth in Plutonium-Bismuth Solutions

Bismuth analytical methods were investigated for the purpose of selecting procedures which are satisfactory for the analysis of solutions containing plutonium and bismuth. The gravimetric procedure which is recommended for samples containing these two elements includes removal of the plutonium by peroxide precipitation, separation of the bismuth by precipitation with sodium carbonate, and final ignition of the bismuth as a phosphate. Necessary equipment and experimental technique are described. In the analysis of eight known samples by the recommended method, the average recovery of bismuth was 99.76 percent, with a standard deviation of 0.22 percent. The known samples contained about 35 mg of bismuth and 25 mg of plutonium. For similar samples in routine work, the confidence limits at the 95 percent level for the average of triplicated determinations are +- 0.30 percent of the bismuth in the the sample. Other methods investigated and having possible application for some Pu-Bi analysis problems include electrodeposition of bismuth on a mercury cathode and gravimetric analysis with BiCr(CNS)6 as the weighed product.
Date: September 15, 1951
Creator: Bergstresser, K. S. (Karl Samuel), 1909-2004
Object Type: Report
System: The UNT Digital Library
Determination of Cadmium in Plutonium-Cadmium Solutions (open access)

Determination of Cadmium in Plutonium-Cadmium Solutions

Determination of cadmium in plutonium-cadmium solutions was successfully accomplished by separating the plutonium as an insoluble peroxide, evaporating the solution containing the cadmium, and weighing the latter as a sulfate. with 5 t0 20 mg of cadmium and similar amounts of plutonium, the 95% confidence limits for the average of triplicate determinations was to be +- 0.3 percent of the cadmium in the sample. When samples contained as little as 5 mg of cadmium, it was necessary to correct the weight of cadmium sulfate with a carefully determined reagent blank which originated mainly from the action of hydrogen peroxide on glass containers.
Date: September 15, 1951
Creator: Bergstresser, K. S. (Karl Samuel), 1909-2004 & Rex, Elgin H.
Object Type: Report
System: The UNT Digital Library

Photogeologic map, Virgin SE quadrangle, Washington County, Utah

Photogeologic map of the Virgin SE quadrangle, Washington County, Utah
Date: September 15, 1956
Creator: Pillmore, C. L.
Object Type: Map
System: The UNT Digital Library
Some Theoretical Problems Concerning Paramagnetic Substances at Low Temperature (open access)

Some Theoretical Problems Concerning Paramagnetic Substances at Low Temperature

Technical report discussing six problems in paramagnetic substances at low temperatures: 1) The Kramers degeneracy; 2) The quenching of orbital motion; 3) Curie constants of CuSO4∙5H2O; 4) Super exchange in CuSO4∙5H2O; 5) The specific heat of CuSO4∙5H2O; and 6) Nuclear interactions of paramagnetic ions. The discussion of these problems brings to light the general principles involved and the general principles can then help understanding of many low temperature phenomena in the paramagnetic salts.
Date: September 15, 1950
Creator: Jauch, Josef M. (Josef Maria),1914-1974.
Object Type: Report
System: The UNT Digital Library
Liquid Reactor Fuels: Bismuth-Uranium System (open access)

Liquid Reactor Fuels: Bismuth-Uranium System

Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.
Date: September 15, 1950
Creator: Bareis, D. W.
Object Type: Report
System: The UNT Digital Library
Unit for Continuous Separation of U233 From Thorium Fluoride (open access)

Unit for Continuous Separation of U233 From Thorium Fluoride

Technical report outlining a preliminary design for carrying out the process of producing U233 from Th232.
Date: September 15, 1950
Creator: Dwyer, O. E.
Object Type: Report
System: The UNT Digital Library
Energy transport control in window systems (open access)

Energy transport control in window systems

None
Date: September 15, 1976
Creator: Berlad, A. L.; Salzano, F. J. & Batey, J.
Object Type: Report
System: The UNT Digital Library