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The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium

Description: Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information.
Date: April 21, 1950
Creator: Yaggee, F. L. & Untermyer, Samuel, 1912-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report [for] October, November, and December, 1952

Description: This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.
Date: December 31, 1952
Creator: Foote, Frank G. & Schumar, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Development of Equipment and Methods for Centrifugally Casting Reactor Fuel Slugs

Description: This technical report describes the design and construction of equipment and the development of methods for multiple mold, centrifugal casting of reactor fuel slugs. Advantages of the centrifugal casting method over the conventional fabrication methods were found to be (1) fewer operations, (2) fewer and more easily recovered residues, (3) less expensive equipment, and (4) the production of fuel slugs in shapes and in alloys not well adapted to other methods of manufacture. The method consisted… more
Date: September 29, 1953
Creator: Shuck, Arthur B., 1918-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test

Description: The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.
Date: April 17, 1952
Creator: Shuck, Arthur B., 1918-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plaster of Paris Replicas of Reactor Fuel Slugs

Description: A method is described for preparing plaster of Paris replicas of irradiated fuel slugs. An impression mold is made by pouring the plaster about a fuel slug held in a specially designed holder. The slug is removed from the holder and the impression mold issued to cast a replica, also made of plaster of Paris. The replicas, including one end only, are accurate reproduction of the original slug for surface features down to about one-half mil and for dimensions within one or two mills. Two dental i… more
Date: June 12, 1953
Creator: Deily, George J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim Report: Faret Experimental Program

Description: From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980… more
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Manufacture of Enriched ZPR-III Fuel Plates

Description: This report is essentially a procedural account of the fabrication of certain enriched ZPR-III fuel plates for use in the ANL fast critical experiments at Arco, Idaho. A total of 208.92 kilograms of fully enrich, unalloyed uranium was processed. Of this amount 202.74 kilograms was received in the form of Oak Ridge type reduction buttons and 6.18 kilograms as pressed-powder plates. The completed fabrication consisted of 720 rectangular fuel plates having the nominal dimensions 3in. x 2in. x 1/8i… more
Date: October 1956
Creator: Yaggee, Frank L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Attack on Uranium by Lithium at 600 C

Description: The tests described in this report were static tests devised to afford a basis for a quick evaluation of the resistance of uranium to attack by lithium. The work was done at the same time as the tests of beryllium, thorium, and various engineering metals in lithium (described in ANL-4990); but the results with uranium are given in the present classified report so that the results of the other tests can be published as an unclassified document. The procedure for carrying out the tests is describ… more
Date: October 13, 1950
Creator: Wilkinson, Walter D. & Yaggee, Frank L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Techniques for X-Ray Examinations of End-Weld Closures and Can-to-Cap Brazes on CP-6 Type Fuel Elements : Final Report -- Metallurgy Program 7.7.7

Description: A fuel element assembly in which a uranium slug is bonded to an impact extruded aluminum can by means of aluminum-silicon eutectic, and in which the can is capped with a thin aluminum disc, brazed and welded to the can, may contain,(a) imperfections common to brazed and welded metal sections, and (b) inhomogeneities arising from oxidation of uranium, and alloy formation between uranium, aluminum and silicon.
Date: January 20, 1954
Creator: Sidhu, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Autoclave Testing of Mechanically Jacketed Thorium Slugs In Water

Description: Water corrosion tests on mechanically jacketed and pinholed thorium slugs show that these slugs fail in a manner similar to that observed for mechanically jacketed and tested uranium slugs. The proposed mechanism for the water corrosion of these jacketed slugs is analogous to the water corrosion mechanism of jacketed uranium slugs presented in the project lecture. A bare thorium slug appeared to be more resistant to corrosion by water than a mechanically jacketed slug during the first half of t… more
Date: January 29, 1953
Creator: Yaggee, Frank L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Growth Rates and Microstructural Characteristics of 300 C Rolled Uranium Rods on Thermal Cycling

Description: The thermal cycling growth and the accompanying metallographic changes were studied in 300 [degree] C rolled uranium rods up to 3000 cycles. The growth rate was found to decrease at the higher cycling levels. Project-grade material developed substantial porosity during cycling; high purity material showed no evidence of porosity.
Date: May 1956
Creator: Chiswik, H. H. & Mayfield, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Metal Purity and Heat Treatment on the Corrosion of Uranium in Boiling Water

Description: Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were found to have higher values almost by a factor of two then previously reported corrosion rates of uranium. Mallinckrodt biscuit metal showed corrosion rates in the same medium somewhat lower than reactor grade uranium, and high purity metal prepared at Argonne National Laboratory corroded considerably less rapidly than the biscuit metal.
Date: April 14, 1953
Creator: Draley, Joseph Edward, 1919- & McWhirter, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Development Program Progress Report: November 1965

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: December 27, 1965
Creator: Adams, R. M. & Glassner, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Deposition of Corrosion Products by Cataphoresis

Description: This report is a record of experimentation conducted intermittently over a period of two years and directed toward preventing deposition of transport corrosion products on fuel elements and other critical components in high-temperature, circulating water nuclear reactor. It includes the postulated mechanism for deposition, a description of experimental equipment, experimental data, results obtained from the experiments, and recommendations for future study.
Date: June 25, 1953
Creator: Fagan, Walter
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Report on Corrosion of Low-Uranium, Zirconium-Base Alloys

Description: Tests were made to determine the effects of heat treatment and composition on the corrosion resistance of low-uranium, zirconium-base alloys to water at 600F. A total of 57 compositions were tested. The zirconium alloys contained up to 9% natural uranium plus small amounts of tin, antimony, lead, bismuth, yttrium, beryllium, germanium, niobium, nickel, and aluminum in various combinations. Data are presented in both tabular and graphical form. The effect of heat treatment on corrosion resistanc… more
Date: October 1953
Creator: Dwight, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Coated Cast Iron Crucible for use with Eutectic Al-Si Alloy in the Temperature Range 595°-650°C

Description: The feasibility of the coated metal crucible as a container for eutectic Al-Si alloy has been proven by test. Small, enamel-coated cast iron pots has been proven by test. Small, enamel-coated cast iron pots have successfully withstood the chemically aggressive Al-Si alloy and the adverse influence of an oxidizing atmosphere for a period of 3 months at 725°C. A similarly coated castiron crucible containing 450 pounds of eutectic Al-Si alloy was successfully tested for 144 days in a jacketing ope… more
Date: November 1957
Creator: Yaggee, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Casting of Blanket Bricks, Ring, Plug, and Control Rods for the Experimental Breeder Reactor (CP-4)

Description: The cup assembly of the Experimental Breeder Reactor (EBR) consists of blanket bricks, inner rings, and safety plug, all of natural uranium. The design of the finish machined brick is shown in Figure 1. These pie shaped bricks when stacked together, 12 bricks arranged in circular form and stacked seven rings high, comprise the cylindrical portion of the outer blanket, 17.875" I.D. x 30.875" O.D. after machining and canning. The inner ring, which is shown in Figure 2, fits inside the bottom laye… more
Date: March 19, 1953
Creator: Macherey, Robert E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature

Description: This report describes corrosion rate of uranium in hydrogen-saturated water appears to be constant with respect to time after a brief induction period and to involve only one type of over-all reaction, in which pitting effects are slight or nonexistent.
Date: May 14, 1952
Creator: McWhirter, J. W. & Draley, Joseph Edward, 1919-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report January, February and March, 1956

Description: The EBWR loading requires a total of 888 plates. It is anticipated that approximately 1000 plates will have to be produced to obtain the number of acceptable plates required for the loading. To the end of this quarter, 568 cladding billet cores acceptable with respect to chemical composition and physical soundness had been cast; this number represents 78% of the total number of cores cast. Approximately 75% of the Zircaloy-II stock required has been rolled, and about 55% of the cladding compone… more
Date: June 1956
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Development Program Progress Report: May 1966

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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