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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shut down, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The general arrangement of the heat exchanger described in this report presents a conventional design utilizing known materials and existing methods of fabrication. In further consideration of all concepts, designs and analyses developed during this period of the program, it is felt that this preliminary design will provide an intermediate sodium heat exchanger of lower cost and more reliable operation.
Date: February 28, 1959
Creator: Alco Products (Firm)
Partner: UNT Libraries Government Documents Department
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Bare Beryllium Extrusion Using Graphite Introductory Cones

Description: The following document describes the process of rare beryllium extrusion using graphite introductory cones with the purpose of finding a lubricant which would decrease excessive friction between the billet and prose parts.
Date: June 28, 1949
Creator: Arnold, Samuel V.
Partner: UNT Libraries Government Documents Department
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K [infinity] in Uranium - Water Lattices

Description: This report follows experiments on K[infinity], measuring the element for several red sizes, enrichments, and water-to-uranium volume ratios-(1, 2), by making use of the relation k[infinity] = 0M-[2]B-[2] (M-2 = migration area, B = buckling). The purpose of this report is to compare the experimental data for k[infinity] with values calculated from the four-factor formula k[infinity] = [eta][epsilon]pf.
Date: July 28, 1955
Creator: Auerback, T.
Partner: UNT Libraries Government Documents Department
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A Further Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.
Date: June 28, 1957
Creator: Banks, William F.
Partner: UNT Libraries Government Documents Department
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Tentative Procedures for Analysis of HCP Process Materials

Description: Abstract: The procedures recommended for analysis in Department 190 Laboratories, in the Limits Control Laboratory, and in the Analytical Development Laboratories, of all process materials from the HCP cycle are presented in a stepwise manner. A description of the characteristics of each sample type along with a brief description of factors involved in the Analytical Quality Control program is included.
Date: May 28, 1947
Creator: Belknap, Herbert J.; Nessle, G. J. & Grimes, W. R.
Partner: UNT Libraries Government Documents Department
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Secondary Missiles Generated by Nuclear-Produced Blast Waves

Description: Report from Operation Plumbob regarding an experiment investigating secondary missiles created by blast waves from nuclear detonations of three different yeilds.
Date: October 28, 1963
Creator: Bowen, I. Gerald; Franklin, Mary E.; Fletcher, E. Royce & Albright, Ray W.
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Description: Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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Critical Ionization of Potentials of Uranium Hexafluoride

Description: Introduction: "The extensive use of uranium hexafluoride in the Nier-type mass spectrometers, where the ionization is produced by slow electrons, made a knowledge of the ionization potentials of the various ions desirable. This information was not available and work was accordingly begun to secure such data. The first measurement was made with a VGIA ion gauge and has been described in TEO report CD-310. With this apparatus it was not possible to identify the ionization products and it was presumed that the value reported was for the UF5 ion. When time and equipment became available, the work was continued and the critical potentials of the singly-charged ions determined."
Date: November 28, 1955
Creator: Cameron, Angus Ewan, 1906- & White, J. R.
Partner: UNT Libraries Government Documents Department
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Progress Report for the Month of February, 1947 : Contract No. W-38-094-Eng-27

Description: This report for February, 1947 describes progress in chemical and spectrographic analysis, chemical work, phase identification, and ore dressing and pyrometallurgical studies.
Date: February 28, 1947
Creator: Center, E. J.; Nelson, H. R.; Pray, H. A.; Richardson, A. C. & Sullivan, J. D.
Partner: UNT Libraries Government Documents Department
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Response of Protective Vaults to Blast Loading

Description: A reinforced-concrete steel-plate-lined vault and steel vault door were exposed to a nuclear detonation (shot Priscilla, about 37 kt, balloon suspended, at 700 ft) at the predicted 75-psi peak incident pressure level (1150 ft from Ground Zero). The vault was designed by the ultimate-strength theory to utilize the additional strain energy available in the elastoplastic and plastic ranges. Flexural and thrust capacities were determined, and shear capacity was computed. It was established that above-ground structures can be designed and constructed to survive the pressure levels experienced by this structure. The vault and door provided adequate blast and thermal protection for normal usage, and the structure was adequate to resist overturning and excessive sliding under conditions of the test.
Date: May 28, 1962
Creator: Cohen, Edward; Laing, E. & Bottenhofer, A.
Partner: UNT Libraries Government Documents Department
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An Ion Exchange Study of Possible Hybridized 5f Bonding in the Actinides

Description: A study was conducted on the elution behavior of curium (III), americium (III), plutonium (III), actinium (III), plutonium (IV), neptunium (IV), uranium (IV), thorium (IV), neptunium (V), plutonium (VI), uranium (VI), lanthanum (III), cerium (III), europium (III), ytterbium (III), ytterium (III), strontium (II), barium (II), radium (II), cesium (I) with 3.2 M, 6.2 M, and 12.2 M HCI solutions from Dower-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. In order to explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5g-ortibals in the actinide elements.
Date: August 28, 1951
Creator: Diamond, R. M.; Street, K., Jr. & Seaborg, Glenn T. (Glenn Theodore), 1912-1999
Partner: UNT Libraries Government Documents Department
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Digestion and Filtration of Leached Zone in Pilot Plant

Description: Introduction: The present report summarizes pilot plant operations on the sulfuric acid digestion of -200 mesh leached zone and filtration of the digested slurry for the period May 5, 1952 through August 7, 1953.
Date: February 28, 1955
Creator: Dugger, Gordon L.; Adams, J. B. & Bart, Roger
Partner: UNT Libraries Government Documents Department
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Wall and Bulk Temperatures for Fluids Flowing in Concentric Annuli

Description: From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."
Date: May 28, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Multiplication of Enriched Loading in Exponential Pile

Description: This report refutes earlier calculations made in the flux level of exponential piles. The results of the earlier calculations made on subcritical assemblies using critical assembly equations are in error. The calculations used in this report were more successful.
Date: September 28, 1953
Creator: Farrand, W. B. & Lloyd, R. C.
Partner: UNT Libraries Government Documents Department
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High Energy Proton Spallation--Fission of Uranium

Description: The fission and spallation reactions caused in uranium by bombardment with high energy protons (340 to 350 Mev) were investigated. The reaction products were separated from the target by chemical processes and identified by their radioactive properties. The relative yields of the observed fission products were measured, and the results plotted as a function of mass number. Several of the spallation products were identified and their yields estimated.
Date: May 28, 1951
Creator: Folger, R. L.; Stevenson, P. C. & Seaborg, Glenn T. (Glenn Theodore), 1912-1999
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1952

Description: This quarterly progress report describes the ongoing research at the Metallurgy Division at the Oak Ridge National Laboratory. In particular, this report discusses the thorium research program, the slug problem, the preferred orientation and anisotropy in metals, fundamental studies of alloying, and the ANP program.
Date: August 28, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridges, W. H.
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of Graphite

Description: Technical report outlining the differences in conductivity of AGOT graphite and AGHT graphite.
Date: November 28, 1949
Creator: Garth, R. C. & Sailor, V. L.
Partner: UNT Libraries Government Documents Department
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The Chlorination of TO₃

Description: Abstract: The applicability of specific mixtures and organic chlorocarbons in general toward the chlorination of TO₃ has been tested by means of reactions is sealed glass tubes. The results show that thionyl chloride mixed with tetrachloroethylene or a bromothane of the tyoe CHBrC12 will produce TCI4 directly. This same result is produced by CBr2C12 alone.
Date: December 28, 1945
Creator: Gavlin, Gilbert; Hubbard, J. V. & Clewett, G. H.
Partner: UNT Libraries Government Documents Department
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Determination of the Molecular Weight of "Tuballoy Pentachloride"

Description: The following report describes methods used to interpret analytical results of the molecular weight of tuballoy pentachloride.
Date: February 28, 1946
Creator: Goren, H. L.; Lowrie, Robert Sydney & Hubbard, J. V.
Partner: UNT Libraries Government Documents Department
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