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Atomic Energy Commission Reports
311
NACA Research Memorandums
115
AEC research and development report
89
Hanford Works Reports
71
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58
NACA Technical Reports
46
North American Aviation Reports
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Health and Safety Laboratory Reports
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Salt Bath Heat Transfer Rates for Uranium Plate
Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date:
February 1, 1962
Creator:
Burditt, R. B.
Object Type:
Report
System:
The UNT Digital Library
The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements
The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date:
November 1, 1961
Creator:
Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
Object Type:
Report
System:
The UNT Digital Library
Intergranular Crack Propagation Rates in Sensitized Type 304 Stainless Steel in an Oxygenated Water Environment
Intergranular stress-corrosion crack (IGSCC) propagation rates were measured in three heats of sensitized Type 304 stainless steel (SS) as a function of sensitization in an environment of high-purity water with 8 ppm oxygen, using a fracture mechanics approach. Specimens were sensitized using controlled furnace heat treatments and the degree of sensitization was measured by the electrochemical potentiokinetic reactivation (EPR) method. Active loading tests were performed on standard specimens over a range of intensities. Crack lengths were determined by compilance measurements using in-situ high-temperature clip gage or LVDT methods, optical metallography on the side faces of the specimen, and fractography of the cracked surface after completion of the tests. The optical metallography measurements did not provide useful estimates of crack lengths, because large variations in IGSCC propagation across the thickness of the specimens occurred. The effects of the degree of sensitization on the IGSCC propagation rate are obscured by the data scatter. However, it seems clear that these variables do not lead to order-of-magnitude changes in the crack propagation rate.
Date:
December 1, 1983
Creator:
Park, J. Y. & Shack, W. J.
Object Type:
Report
System:
The UNT Digital Library
Transient Temperature Simulation of Reactor Primary Loop
Report issued by the APDA over simulator studies conducted on their Developmental Fast Breeder Reactor. The simulator studies were "designed to predict both the normal and abnormal operating characteristics of the APDA Developmental Fast Breeder Reactor" (p. 1). This report includes tables, and illustrations.
Date:
February 1, 1956
Creator:
Olson, Richard G. & Ritchie, Donald J.
Object Type:
Report
System:
The UNT Digital Library
Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors
Report issued by the APDA over studies conducted on Doppler coefficient fast reactors. Calculations, methods, and results of the studies are presented. This report includes tables, and illustrations.
Date:
November 1, 1963
Creator:
Fischer, E. A.
Object Type:
Report
System:
The UNT Digital Library
Coal Resources of the United States
A report about the United States's coal supply. The U.S. has 25 percent of the world's identified coal resources and about 20 percent of the world's estimated total coal resources.
Date:
January 1, 1974
Creator:
Averitt, Paul
Object Type:
Report
System:
The UNT Digital Library
The Identification and Determination of Trace Amounts of Rare Earth Elements in Graphite by Neutron Activation
Abstract: "A method is described for the identification and quantitative determination of trace amounts of rare earths in graphite by measurement of the energies and decays of the activities induced by neutron irradiation. The specific rare earth elements identified are europium and samarium. During the development of this method, the half-lives of Eu-152 and Sm-153 were determined. These are reported as 9.32 +/- 0.04 hours and 46.34 +/- 0.23 respectively."
Date:
September 1, 1949
Creator:
Ross, A. M.
Object Type:
Report
System:
The UNT Digital Library
Exploratory Scavenging Studies for the Decontamination of Redox Solutions
From introduction: "This report is concerned with exploratory experiments designed to studies the efficiency of a number of scavengers for zirconium and niobium adsorption and to provide preliminary information on the best conditions to employ on the most satisfactory of those scavengers studied, namely Super Filtrol FO. The data in this report include data obtained through October, 1949, and are by no means considered to be final. The investigation is currently being actively continued."
Date:
May 1, 1950
Creator:
Roake, W. E. & Lowe, C. S.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Rates of Mild and Stainless Steels Exposed in Redox Stream IAW : (ANL, June 1, 1948 Flowsheet)
Introduction: In order to determine the relative corrosion resistance of welded mild and stainless steels in Redox Stream IAW neutralized to pH 0, 2, and 10 a test program, described below, has been carried out.
Date:
November 1, 1949
Creator:
Koenig, W. W.
Object Type:
Report
System:
The UNT Digital Library
A comparison of two methods for the spectrochemical analysis of plutonium
Report describing the methods, discrepancies, accuracy of methods, and conclusions of two different analytical methods of spectrochemical analysis of plutionium.
Date:
February 1, 1950
Creator:
Van Tuyl, H. H.
Object Type:
Report
System:
The UNT Digital Library
The Coulometric Determination of Acid
Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."
Date:
March 1, 1950
Creator:
Carson, W. N. & Ko, Roy
Object Type:
Report
System:
The UNT Digital Library
The Development of Plutonium Electrodeposition Methods : Interim Report
From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."
Date:
March 1, 1950
Creator:
Schwendiman, L. C.
Object Type:
Report
System:
The UNT Digital Library
Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent
Objective: "The laboratory equilibrium study RC-E-1 described in this report was carried out to obtain uranium equilibrium curves at various concentrations of nitric acid and of TBP."
Date:
May 1, 1950
Creator:
Clagett, Fred
Object Type:
Report
System:
The UNT Digital Library
Mechanical Properties of Iodide Zirconium Alloys
Introduction: "The tensile properties, hot hardness, impact strength; and corrosion resistance of some arc-melted, iodide zirconium alloys have been determined. The alloys investigated include binary alloys of zirconium containing zero to five per cent tin, binary alloys of zirconium containing zero to 0.14 per cent nitrogen, and ternary alloys of zirconium containing tin and nitrogen, tin and uranium, and uranium and beryllium."
Date:
November 1, 1952
Creator:
Schwope, A. D. & Chubb, Walston
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements
Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."
Date:
December 1, 1952
Creator:
Harman, Cameron G.; Ferrell, Edward Francis.; Wagner, H. E. & Quirk, J. F.
Object Type:
Report
System:
The UNT Digital Library
Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux
From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
Date:
March 1, 1965
Creator:
Suo, M.; Bergles, Arthur E.; Doyle, Edward F.; Clawson, L. & Goldberg, P.
Object Type:
Report
System:
The UNT Digital Library
An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building
Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."
Date:
May 1, 1959
Creator:
Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Object Type:
Report
System:
The UNT Digital Library
Magnetic Properties of Insulators : Quarterly Report No. 7 Covering the Period from August 16, 1962 to November 15, 1962
The following quarterly progress report covers the period of August 15 to November 15, 1962. It summarizes three activities of the group. The first part is the optical study of the absorption band associated with the F-center in RbCl. The second part discusses some elementary calculations of the spin-lattice relaxation times, the primary purpose of this step is to indicate the nature of the theoretical problem faced and show the large gap between the value calculated theoretically and measured experimentally. The last section includes more data on the shape and recovery of the hole in a EPR band associated with the F-center in KCl.
Date:
December 1, 1962
Creator:
Markham, Jordan J.
Object Type:
Report
System:
The UNT Digital Library
Magnetic Properties of Insulators : Quarterly Report No. 8 Covering the Period from November 16, 1962 to February 15, 1963
The following quarterly progress report covers the period from November 16, 1962 to February 15, 1963. This report summarizes three activities that study the ratio of the maximum absorption of the K band to the maximum absorption of the F band has been made in additively colored and [gamma]-irradiated rubidium chloride.
Date:
March 1, 1963
Creator:
Markham, Jordan J.
Object Type:
Report
System:
The UNT Digital Library
Grain Refinement of Uranium by Alloying
Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys having nominal compositions of 0.01, 0.1, and 1.0 at.% were made with most of the elements, and in addition, 12 ternary and quaternary alloys were made. The alloys were cast, rolled to 7/8-inch-diameter bars, heat treated, and examined for grain size.
Date:
June 1, 1951
Creator:
Saller, Henry A.; Keeler, J. R. & Eddy, N. S.
Object Type:
Report
System:
The UNT Digital Library
Jacketing of Uranium for High-Temperture Service
From introduction: "The work covered in this report is a portion of the experimental research undertaken for the design of a uranium-containing metallic fuel rod for operation in air at 1090 C...This report deals with that phase which involved the testing and evaluation of various metals as barrier costs between uranium alloys, and low-carbon steel. The work is of a preliminary nature and is concerned more with a comparison of the various barrier metals than with the acquisition of numerical data, e.g., diffusion coefficients."
Date:
June 1, 1951
Creator:
Saller, Henry A. & Stacy, J. T.
Object Type:
Report
System:
The UNT Digital Library
Progress Report for the Month of January, 1952
This progress report of the Battelle Memorial Institute covers information in many categories. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
Date:
February 1, 1952
Creator:
Russell, H. W.; Nelson, H. R. & Dayton, R. W.
Object Type:
Report
System:
The UNT Digital Library
Experimental Fabrication of a Lightweight Control Rod
Abstract: "The possibility of fabricating a lightweight control rod from one of several high cross-section materials was investigated. The major effort was directed toward the development of a titanium-clad rod containing a composite core of 25 weight per cent Gd2O3 in a matrix of titanium. Experimentation on both subscale and full-scale control-rod cores showed that the fabricating behavior of the two was not analogous. To roll the full-scale core successfully, it was necessary to lower the oxide content to 17 weight per cent. Subscale investigations were also carried out on titanium-cadmium, titanium-lanthanum, and titanium-gadolinium alloys."
Date:
July 1, 1952
Creator:
Saller, Henry A.; Stacy, J. T. & Keller, D. L.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod
Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."
Date:
October 1, 1954
Creator:
Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
Object Type:
Report
System:
The UNT Digital Library