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Glasscock County, Texas: Records of wells, drillers' logs, and 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:
November 22, 1937
Creator:
United States. Work Projects Administration.
System:
The Portal to Texas History
The Input Admittance of a Ring Circuit
"A ring circuit is a succession or two-port networks and at least one three-port network, each feeding the next at one port and the last feeding the first so that the sequence closes on itself leaving at least one input port. The input admittance is derived in terms ef various matrices describing the circuit for one- and two-input port rings."
Date:
January 22, 1958
Creator:
Rees, J. R.
System:
The UNT Digital Library
Radioactivation Analysis
The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radiation and half-life, it is possible, through radiochemical measurements following radioactivation, to devise a method of analysis which is very specific for particular elements. Whenever necessary, the radioisotope is separated by chemical means and its radioactivity is then measured by some type of radiation counter.
Date:
September 22, 1961
Creator:
Leddicotte, G. W.
System:
The UNT Digital Library
Internally Cooled Molten-Salt Reactors
The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date:
June 22, 1959
Creator:
Lackey, M. E.
System:
The UNT Digital Library
Hexone Extraction-Coulometric Titration of Uranium
Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date:
June 22, 1959
Creator:
Blevins, E. L.
System:
The UNT Digital Library
Report of Fire in Laboratory Hood, Wing I, Building 4500
The fire involved approximately 30 liters of isopropyl alcohol as a result of the ignition of about 16-18 liters of isopropyl alcohol and a slurry of thoria and ammonium nitrate in a 20-liter glass carboy. This material was undergoing a volume reduction by boiling in a floor-type metal hood with Plexiglas sides and 3 sliding door on the front of ordinary glass. The alcohol vapor was vents directly into the hood (Fig1.)
Date:
May 22, 1959
Creator:
Lain, J. E. & Hungerford, T. W.
System:
The UNT Digital Library
Preliminary Report on 2% U235-Enriched UF4-C25H52 Critical Assemblies
A series of critical experiments with blocks of 2% U235-enriched UF4-C25H52 has been initiated at the ORNL Critical Experiments Facility. Thus far assemblies with H:U235 atomic ratios of 195 and 294 have been built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres have been determined to be 16.3 and 8.5 kg of U235 for fuel mixtures with H:U235 atomic ratios of 195 and 294, respectively. The minimum critical masses for unreflected spheres of these two fuel mixtures are 24.3 and 12.7 kg of U235, respectively.
Date:
April 22, 1959
Creator:
Mihalczo, J. T.; Lynn, J.J.; Scott, Dunlap & Connolly, W. C.
System:
The UNT Digital Library
In-Reactor Autoclave Corrosion Studies II : Autoclave Z-19
In order to test the effect of chromate ion on the corrosion of Zircaloy-2 a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm Cr (VI) was autoclaved with rocking at 280 C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the a rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (VI) had no significant effect on the radiation corrosion of Zircaloy-2 by enriched uranyl sulfate solutions. However, the data are not conclusive and may be interpreted as showing a low corrosion rate for a limited period (i.e. a short term inhibition) followed by a correspondingly rapid corrosion.
Date:
March 22, 1957
Creator:
Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
System:
The UNT Digital Library
In-Reactor Autoclave Corrosion Studies : LITR I. Outline of Methods and Procedures
During the development of in-reactor corrosion experiments three types of bomb designs have been developed for following quantitatively the consumption of oxygen in a bomb which is fabricated from the particular metal under test. The bombs are designed so as to be rocked continuously during their in-reactor exposure, consequently agitating the uranium salt solution contained in the bomb and permitting gentle movement of the solution past metal specimens and other corroding surfaces. The oxygen pressure is produced within the bomb at the beginning of the run either by the withdrawal of gas from an oxygen tank or by the decomposition of hydrogen peroxide added just prior to closure. Temperature measurements are obtained by mans of thermocouples placed in a well within the bomb body or, in the latest design, there will also be thermocouples staked at several points on the outer wall of the bomb. The assembly is inserted in an experimental access hole in the reactor, brought up to a predetermined operating temperature by means of an electric furnace in close contact with the bomb, and allowed to remain for the desired amount of exposure to reactor radiation. Periodic measurements of temperature and pressure are made and the bomb …
Date:
May 22, 1957
Creator:
Warren, K. S. & Davis, R. J.
System:
The UNT Digital Library
Summary of Corrosion Data for HRT Mockup Operational Period Ending November 5, 1956
The operation of the HRT mockup was on 0.042m UO2SO4, 0.024m H2SO4, and 0.005m CuSO4 at 280 C and 1400 psi pressure. with the O2 content at near 500 ppm. The pump showed bearing wear and high corrosion. The letdown heat exchanger was removed from the mockup and sectioned. The metallographic examination revealed corrosion. Results of corrosion runs on Ti, zircaloy-2, and stainless steel are given.
Date:
May 22, 1957
Creator:
Wacker, R. E. & Griess, J. C.
System:
The UNT Digital Library
Deflection Equations for Various Loading of Circular-Arc Curved Beams
In analyzing stresses, deflections, and forces in piping and certain structural systems, it is useful to have a set of equations giving the deflections at any point of a curved beam in terms of the various loads acting on the beam. This technical report presents the deflection equations for a curved circular-arc beam of variable length. The cases treated include in-plane and out-of-plane bending due to forces and moments applied to the end of the beam in three principal directions, and uniformly distributed loads applied along the beam in these three directions. Deflections were calculated by the strain energy method using Castigliano's theorem.
Date:
April 22, 1957
Creator:
Platus, D. L. & Greenstreet, B. L.
System:
The UNT Digital Library
The Choice in Thorium Oxide Slurries for the Prevention of Caking in Circulating Systems
A qualitative theory for cake formation in ThO2 slurries is presented. The sphere formation which occurs in "Standard" slurry can be explained on the same basis. The irregular and unpredictable yield strength is easily fitted into the theory. On the basis of this theory, the writer has been led to the conclusion that only colloidally stable slurries, or slurries with crystallites or comminution-resistant particles which are large enough to overcome colloidal effects (probably larger than 0.1u) can be used with assurance in the ThO2 reactor system. This conclusion holds for 300 gm/kg slurries as well as for more concentrated mixtures.
Date:
April 22, 1957
Creator:
Lyon, R. N.
System:
The UNT Digital Library
Supplement to: Curve Plotting Routine for the Oracle (57-4-56)
A general program has been written to plot curves on the Oracle curve plotter. The supplement includes changes to slow down some of the loops and minimize the possibility of read-around errors and changes to handle special cases.
Date:
October 22, 1957
Creator:
Lietzke, M. P.
System:
The UNT Digital Library
In-Reactor Autoclave Corrosion Studies. II, Autoclave Z18
In order to test the effect of chromate ion on the corrosion of Zircaloy-2, a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm of Cr (VI) was autoclaved with rocking at 280 degrees C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (VI) had no significant effect on the radiation corrosion of Zircaloy-2 by enriched uranyl sulfate solutions. However, the data are not conclusive and may be interpreted as showing a low corrosion rate for a limited period (i.e. a short term inhibition) followed by correspondingly rapid corrosion.
Date:
March 22, 1957
Creator:
Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
System:
The UNT Digital Library
HRT Sampler Development
A prototype sampler for obtaining samples of high radioactive UO2SO4 solution for use in the HRT is presented. It was successfully operated in conjunction with a low pressure water system and a high pressure, high temperature UO2SO4 system.
Date:
January 22, 1957
Creator:
Hannaford, B. A.
System:
The UNT Digital Library
Annual Report of the Boy Scouts of America: 1961
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1961, activities, public relations, finance, organizational leadership, and other information about scouting programs.
Date:
March 22, 1961
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1955
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1955, activities, organizational leadership, and other information about scouting programs.
Date:
March 22, 1956
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1951
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1951, activities, public relations, programming, finance, organizational leadership, and other information about scouting programs.
Date:
March 22, 1952
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1948
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1949, activities, organizational leadership, and other information about scouting programs.
Date:
March 22, 1949
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1947
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1947, activities, honors, finance. public relations, organizational leadership, and other information about scouting programs.
Date:
March 22, 1948
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1927
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1927, activities, ideals, organizational leadership, and other information about scouting programs.
Date:
May 22, 1928
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Pressure Drop Along a Fuel Cycle Fuel Assembly - Various Orifice Configurations
The objective is to establish, from test results, the relationship between pressure loss and orifice configuration, mass rate, and steam quality, for a Fuel Cycle fuel assembly.
Date:
May 22, 1961
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
Pilot Plant Tests on Anaconda Ore From the Grants District, Grants, New Mexico
A series of pilot plant runs were made on the Jackpile ore, Jackpile mixed blend, Jackpile-Poison Valley blend, and Jackpile-Arrowhead blend.
Date:
July 22, 1954
Creator:
Hollis, R. F.; Abrams, Charles S.; McArthur, C. K.; Izzo, T. F. & Wilson, H.
System:
The UNT Digital Library
Recovery of Uranium From High Grade Australian Rum Jungle Uranium Ore
The leaching behavior, thickening and filtering characteristics and recovery of uranium from high grade uranium ore from Rum Jungle, Northern Territory, Australia are described.
Date:
August 22, 1952
Creator:
George, D'Arcy R.
System:
The UNT Digital Library