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10 MWe Sodium Deuterium Reactor Design Report (open access)

10 MWe Sodium Deuterium Reactor Design Report

From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power using a sodium-cooled reactor.
Date: 1959
Creator: Davis, Peter J.
System: The UNT Digital Library
Abilene Fire Department Annual Report: 1959 (open access)

Abilene Fire Department Annual Report: 1959

Annual report of the Abilene Fire Department describing the organization and administration, with updates on goals, activities, and accomplishments during fiscal year 1959.
Date: 1959
Creator: Abilene (Tex.). Fire Department.
System: The Portal to Texas History
Absorption of Radionuclides Applied to Above Ground Plant Parts : Terminal Report (open access)

Absorption of Radionuclides Applied to Above Ground Plant Parts : Terminal Report

The attached list of publications is submitted as a year to year and final report of progress on work accomplished under Contract AT(11-1)-159 from 1950 to 1959. Work was initiated on this project in the spring of 1950 and is still in progress as of the date of this report.
Date: 1959
Creator: Wittwer, S. H. (Sylvan Harold), 1917-2012; Turkey, H. G. & Bukovac, M. J.
System: The UNT Digital Library
Aerodynamic characteristics of the X-15/B-52 combination (open access)

Aerodynamic characteristics of the X-15/B-52 combination

Report presenting an investigation to determine the carry loads and mutual aerodynamic interference effects from high-speed wind-tunnel tests and the drop characteristics of the X-15 through the B-52 flow field from low-speed dynamic-model drop tests and six-degree-of-freedom calculations. The X-15 installation was found to increase drag at cruise conditions by approximately 15 percent.
Date: 1959
Creator: Alford, William J., Jr. & Taylor, Robert T.
System: The UNT Digital Library
Agglomeration Studies in the Low-Pressure Hydrogenation of Coal in a Fluidized Bed (open access)

Agglomeration Studies in the Low-Pressure Hydrogenation of Coal in a Fluidized Bed

Report discussing hydrogenation of coal at a low-pressure displaying results of the experiments.
Date: 1959
Creator: Kawa, Walter; Hiteshue, Raymond W.; Budd, William A.; Friedman, Sam & Anderson, Robert B.
System: The UNT Digital Library
Aging of Al-Li Alloys - Part I (open access)

Aging of Al-Li Alloys - Part I

Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) or the (111) planes of the aluminum matrix were observed in overaged specimens."
Date: January 1959
Creator: Angerman, C. L.
System: The UNT Digital Library
Anodic Precipitation of Tracer Manganese as Dioxide (open access)

Anodic Precipitation of Tracer Manganese as Dioxide

Quantitative recovery of carrier‐free 10−9 M manganese (II) is possible from weakly acidic solutions. The use of lead dioxide as either a non-isotopic carrier or a chemical displacing agent makes possible high recoveries from more acidic solutions.
Date: 1959
Creator: Heintz, Edward A. & Rogers, Lockhart Burgess, 1917-1992
System: The UNT Digital Library
Application of Electrical-Resistivity Surveys to Exploration for Zinc-Lead Deposits, Racine-Spurgeon Area, Newton County, Missouri (open access)

Application of Electrical-Resistivity Surveys to Exploration for Zinc-Lead Deposits, Racine-Spurgeon Area, Newton County, Missouri

Report issued by the Bureau of Mines over surveys conducted on zinc-lead deposits of Newton County, Missouri. Results of the surveys are presented. This report includes tables, maps, and illustrations.
Date: 1959
Creator: Chester, John William
System: The UNT Digital Library
An approach to the study of solid state bonding (open access)

An approach to the study of solid state bonding

The program objective has been to investigate the possible similarity between a bond interface and a grain boundary. The criterion for establishing the similarity of a bond interface and a grain boundary was the migration characteristics of the boundary under the influence of controlled orientation, strain level, temperature and time. In addition, the orientation dependency of the "threshold", or minimum deformation, for bonding would have to be determined. The initial bonding studies were to be made by a "cold welding" technique; subsequently, elevated temperatures bonding would have been attempted. Migration of boundaries was to be observed by high temperature metallographic techniques.
Date: 1959
Creator: Steele, R. K. & Kozol, J.
System: The UNT Digital Library
Asbestos: A Materials Survey (open access)

Asbestos: A Materials Survey

Report issued by the U.S. Bureau of Mines discussing asbestos mining. As stated in the introduction, "this report gives primary consideration to the types and grades of asbestos that are of greatest importance in the program of military preparedness-namely, the spinning grades of chrysotile, both foreign and domestic, and the amosite and crocidolite obtained only from foreign sources" (p. 1). This report includes tables, maps, illustrations, and photographs.
Date: 1959
Creator: Bowles, Oliver
System: The UNT Digital Library
Astron Electron Injection. (open access)

Astron Electron Injection.

None
Date: January 1, 1959
Creator: Christofilos, N.
System: The UNT Digital Library
Bibliography of Published Papers of the Atomic Bomb Casualty Commission (1947-1959) (open access)

Bibliography of Published Papers of the Atomic Bomb Casualty Commission (1947-1959)

References to 193 publications of staff members of the Atomic Bomb Casualty Commission during 1947 through 1959 are listed in both English and Japanese. Author and subject indexes are included.
Date: 1959
Creator: Atomic Bomb Casualty Commission
System: The UNT Digital Library
Bibliography of U.S. Geological Survey Reports on Uranium and Thorium 1942 Through May 1958 (open access)

Bibliography of U.S. Geological Survey Reports on Uranium and Thorium 1942 Through May 1958

A bibliography of reports that pertain to geology, mineralogy, chemistry of uranium or thorium, beryllium, lithium, and other rare elements of interest in the atomic energy program.
Date: 1959
Creator: Soister, Paul E. & Conklin, Dora R.
System: The UNT Digital Library
Biennial Report of the Texas Library and Historical Commission State Library: 1956-1958 (open access)

Biennial Report of the Texas Library and Historical Commission State Library: 1956-1958

Biennial report of the Texas Library and Historical Commission for the years 1956-1958, including the budget and summaries of the library's activities.
Date: 1959
Creator: Texas Library and Historical Commission
System: The Portal to Texas History
Boundary-Layer Displacement Effects in Air at Mach Numbers of 6.8 and 9.6 (open access)

Boundary-Layer Displacement Effects in Air at Mach Numbers of 6.8 and 9.6

"Measurements are presented for pressure gradients induced by a laminar boundary layer on a flat plate in air at a Mach number of 9.6 and for the drag of thin wings at a Mach number of about 6.8 and zero angle of attack. The pressure measurements at a Mach number of 9.6 were made in the presence of substantial heat transfer from the boundary layer to the plate surface. The measured pressure distribution o the surface of the plate was predicted with good accuracy by a modification to insulated-plate displacement theory which allows for the effect of the heat transfer and temperature gradient along the surface on the boundary-layer displacement thickness" (p. 1).
Date: 1959
Creator: Bertram, Mitchel H.
System: The UNT Digital Library
Canning graphite for gas-cooled reactors (open access)

Canning graphite for gas-cooled reactors

From abstract: "A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen-oxygen atmosphere"
Date: 1959
Creator: Paprocki, Stan J.; Carlson, Ronald J. & Bonnell, Paul H.
System: The UNT Digital Library
Canning Graphite for Gas-Cooled Reactors (open access)

Canning Graphite for Gas-Cooled Reactors

A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen--oxygen atmosphere. Fabrication techniques for cladding bare and copper--plated graphite cores either in Type 316 stainless steel or Inconel X were developed. Specimens of the various combinations of core and cladding materials were subjected to simulatedservice conditions and evaluated. In all cases the Type 316 stainless steel-clad specimens failed by carburization and subsequent oxidation in relatively short periods of time. Although considerable trouble was experienced with rupture in the vicinity of the cladding welds during thermal cycling of the Inconel X-clad specimens, this material appeared to be satisfactory in other respects and is considered promising. A specimen of silicon-coated graphite eiad with Type 316 stainless steel was tested by heat treating for 624 hr at 1800 deg F. The silicon coating alloyed with the cladding material, formed a high-silicon diifusion zone, but prevented carburization of the stainless steel. (auth)
Date: January 1, 1959
Creator: Paprocki, S. J.; Carlson, R. J. & Bonnell, P. H.
System: The UNT Digital Library
CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES (open access)

CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A listing of basic references is given. (J.R.D.)
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
System: The UNT Digital Library
Clay in Petroleum-Reservoir Rocks: Its effect on Permeability, with Particular Reference to Tejon-Grapevine Area, Kern County, California (open access)

Clay in Petroleum-Reservoir Rocks: Its effect on Permeability, with Particular Reference to Tejon-Grapevine Area, Kern County, California

Report issued by the Bureau of Mines over studies conducted on clays of petroleum-reservoir rocks in Kern County, California. The effects of water sensitivity of clays are presented. This report includes tables, maps, illustrations, and photographs.
Date: 1959
Creator: Morris, Frank C.; Aune, Quinton A. & Gates, George Laurence
System: The UNT Digital Library
Conversion of Nicaro Nickel Oxide to Nickel Metal (open access)

Conversion of Nicaro Nickel Oxide to Nickel Metal

Report issued by the Bureau of Mines over testing conducted on nickel oxide to produce nickel metal. Details of testing methods and results are presented. This report includes tables, illustrations, and photographs.
Date: 1959
Creator: Mahan, W. M.; Melcher, N. B.; Riott, J. P. & Ostrowski, E. J.
System: The UNT Digital Library
Core Characteristics of Four Army Package Power Reactors (open access)

Core Characteristics of Four Army Package Power Reactors

A brief discussion of the core charteristics of four uranium fuel, pressurized-water type: Army Package Power Reactors, the SM-1, SM-1A, PM-2A, and SW-2, is presented. The characteristics discussed are cell geometry, fuel plates, core geometry, flux distributions, core loading, core burnout, and control reds. Tables and illustrations are included. (auth)
Date: January 1, 1959
Creator: Gallagher, J. G.; Leibson, M. J. & Byrne, B. J.
System: The UNT Digital Library
DARED-1--AN IBM-704 PROGRAM FOR REDUCING DATA FROM FOIL IRRADIATION AND FITTING BY LEAST SQUARES TO BESSEL J$sub 0$ OR COSINE FUNCTION (open access)

DARED-1--AN IBM-704 PROGRAM FOR REDUCING DATA FROM FOIL IRRADIATION AND FITTING BY LEAST SQUARES TO BESSEL J$sub 0$ OR COSINE FUNCTION

A description is given of a code for the IBM-704 computer which reduces and fits by least squares the measurements of radioactivity of a sequence of foils. Corrections for background, counter deadtime, foil weight, and radioactive decay are applied, and readings outside a specified range are rejected. Errors due to statistical fluctuations are computed and off-center ordinates are calculated. Reduced data are then fitted by least squares to the best value of the arguments of Bessel J/sub o/ or cosine functions. Up to 100 foils in a sequence can be handled, and decay times up to 999 min can be accommodated. An IBM-704 computer having 8192 words of core storage is required. No drums or tapes are needed. Running time for a typical 50 point problem involving data reduction alone is 2 min. With least squares fitting, the same problem would require 4 min. (auth)
Date: January 1, 1959
Creator: Jedruch, J. & Saalbach, C.
System: The UNT Digital Library
The Design and Uses of High Flux Research and Test Reactors (open access)

The Design and Uses of High Flux Research and Test Reactors

The need for thermal and fast neutron fluxes in the range of 1 to 5 x l0/ sup 15/ neutrons/cm/sup 2/(sec) for the production of heavy elements such as Cf/ sup 252/ and other special isotopes and for improving the quality of beam experiments, reactor materials testing work, and solid state research has led to plans for the construction of three ultra high flux research reactors. The designs of these and other high flux research reactors are based on the general technology of enriched tank-type reactors; however, they utilize the principle of separate fuel and moderator regions to achieve flux peaking in these regions. Thus, proposed designs take the form of an annular fuel region with internal and external moderating regions or an under moderated core with an external moderator or reflector. In such arrangements, the thermal flux peaks in the moderating regions and the fast flux peaks in the fuel region, which results in maximum fast and thermal fluxes per unit of power. Since most of the moderation of fast neutrons takes place outside of the fuel region, the thermal flux peaking depends on the number of fast neutrons leaking from the reactor core, which in turn depends on …
Date: January 1, 1959
Creator: Lane, J. A.
System: The UNT Digital Library
Determination of the Formation Constant of Indiumacetylacetonate by an Extraction Method (open access)

Determination of the Formation Constant of Indiumacetylacetonate by an Extraction Method

1. The solubility of acetylacetone has been determined in an acetate buffer solution of ionic strength C.1 in relation to pH and temperature. 2. The distribution coefficients of acetylacetone have been determined between chloroform, carbon tetrachloride, benzene and an acetate buffer solution in relation to acetylacetone concentration and pH. 3. The relationship has been established between the rate at which indium acetylacetonate reaches partition equilibrium and the pH, initial acetylacetone concentration in the organic phase, and the different organic solvents. 4. The extent of the extraction of indiumacetylacetonate has been determined for three organic solvents at two acetylacetone concentrations in relation of pH. The independence of the degree of extraction from indium concentration was established in the region between 10(-4) to 10(-6) M. 5. 5. The indium acetylacetone compound was obtained by extraction from organic solvents. 6. The stability constants were calculated by two different methods for the uncharged complex and intermediate complexes; also the constants for the various steps of the dissociation of indiumacetylacetonate.
Date: 1959
Creator: Rudenko, N. P. (Nikolaĭ Petrovich); Stary, I. & de Bruin, H. J.
System: The UNT Digital Library