Collection
Serial/Series Title
Atomic Energy Commission Reports
175
Hanford Works Reports
64
HW (Series)
49
BNL (Series)
36
Brookhaven National Laboratory Reports
36
General Electric Company Atomic Power Reports
36
GEAP (Series)
33
University of California Radiation Laboratory Reports
24
AECU (Series)
19
Los Alamos National Laboratory Reports
16
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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.
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.
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.
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.
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
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.
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
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
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.
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
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.
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.
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.
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.
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.
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.
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.
System:
The UNT Digital Library
The Effectiveness of Spray Cooling
Abstract: "A possible method of cooling a liquid-fuel reactor is by spraying liquid metal through the liquid fuel, and then circulating the liquid metal through a heat exchanger. To evaluate the effectiveness of this cooling method, a few simple experiments were made with mercury sprayed through water. On the basis of the results, it was concluded that this method was intrinsically a low-power-density method, which could not find application except where a low fissionable-material inventory was the dominating requirement in a low-power reactor. Even there, it is thought that a boiling homogeneous reactor might be superior. The results are reported, in spite of their probably lack of value in the reactor program, simply to make the record complete."
Date:
October 1, 1953
Creator:
Dayton, R. W.; Allen, C. M. & Miller, N. E.
System:
The UNT Digital Library
Progress Report for August, 1955
This report of the Battelle Memorial Institute covers information on development regarding various materials.
Date:
September 1, 1955
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
System:
The UNT Digital Library
Nuclear Reactor Project Progress Report, January 1948
This report is a progress report detailing operations and ongoing projects at the Brookhaven National Laboratory. The report describes new developments with buildings and progress regarding ongoing experiments. The report includes photographs showing progress in the construction of the reactor and other images and figures that accompany the descriptions of projects.
Date:
January 1, 1948
Creator:
Borst, L. B. & Fox, Marvin
System:
The UNT Digital Library
Nuclear Reactor Progress Report
Technical report describing the building of safety devices and features for the Oak Ridge reactor by the Reactor Safeguard Committee of the Atomic Energy Commission. Outlines the difficulties encountered in detailed design and construction operations for the facility.
Date:
October 1, 1948
Creator:
Brookhaven National Laboratory
System:
The UNT Digital Library
Continuous Solvent Recovery Process Using Pulse Contacting Column
From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."
Date:
April 1, 1952
Creator:
Ellison, C. V. & Land, J. F.
System:
The UNT Digital Library
Summary of Operating Experience with Decelerating Ion Receivers
From abstract: "The following report presents a summary of operating experience with decelerating receivers for ion beam reception. Sample calculations for design of such a receiver for the isotopes of lithium are presented. Estimates of maximum production and requirements to attain such production are given. The maximum ion beam envisioned is 17 amperes obtained from extrapolation of experimental results."
Date:
April 1, 1952
Creator:
Wilkinson, P. E. & Keim, C. P.
System:
The UNT Digital Library
Static Corrosion Behavior of Construction Materials in an Environment of Liquid Bismuth Base Metals at 550° C
Technical report presenting preliminary results obtained in the static corrosion test program to screen promising construction materials for a proposed liquid fuel power breeder reactor.
Date:
March 1, 1952
Creator:
Cordovi, M. A.
System:
The UNT Digital Library