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Chemistry Division, Section C-II, Summary Report for July, August, and September 1952

Description: This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uraniu… more
Date: January 21, 1953
Creator: Gilbreath, J. R. & Simpson, O. C.
open access

Chemistry Division, Section C-II, Summary Report for July, August, and September 1952

Description: This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uraniu… more
Date: January 21, 1953
Creator: Gilbreath, J. R. & Simpson, O. C.
open access

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.
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Comparative Analysis of ANL High Purity Uranium

Description: In the course of the development at Argonne of high purity uranium metal in ingot form, some questions arose as to the validity of the chemical analyses of some of the impurities (particularly those for carbon, boron, and silicon), with one analytical laboratory reporting concentrations in some instances of an order of magnitude greater than another laboratory. Since the low concentrations of impurities in this material involved, in some cases, the development of modified analytical procedures … more
Date: September 24, 1953
Creator: Blumenthal, B. & Chiswik, H. H.
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Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation

Description: Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
Date: October 1964
Creator: Wilhelm, Donald J.
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Corrosion and Stability Tests on Chemical Poisons in Higher-Temperature Water

Description: Corrosion-stability tests have been made in static autoclaves at 500 and 600F on solutions of compounds having high neutron cross sections to evaluate their usefulness for shutdown purposes. The only compound tested which appeared to be completely stable in 600F water was boric acid. Limited corrosion data did not show it to cause excessive corrosion of zirconium or stainless steel.
Date: September 1, 1953
Creator: Breden, Calvin Rudolph, 1901- & Abers, Alma
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Corrosion of Plutonium Alloys in NaK

Description: A plutonium-aluminum alloy containing 4 atom per cent aluminum showed no attack after exposure to purified NaK for one month at 400 C in the absence of any oxide. The same specimen and other plutonium alloys, including pure plutonium, showed marked deterioration in shorter exposure in the presence of oxide films from a welded stainless steel container. Pure uranium was resistant even in the presence of such oxides.
Date: July 1953
Creator: Hyman, H. H. & Katz, Joseph J. (Joseph Jacob), 1912-2008
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Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Description: Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
open access

Critical Studies with G. E. Type Fuel Elements

Description: The ZPR-I is a facility to study low power critical assemblies using enriched uranium as fuel, having a light water moderator and an essentially infinite water reflector on all sides. The fuel is held in elements 43" long with a 1" square cross section. Any of these elements may be placed in or removed from any position in the reactor tank. Thus, any desired core configuration may be easily obtained.
Date: August 1953
Creator: Martens, F. H. & Helfrich, G. F.
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The Decomposition of Light and Heavy Water Boric Acid Solutions by CP-3' File Radiations

Description: The behavior of light and heavy water solutions of boric acid toward pile radiations has been investigated as a function of boric acid concertation. A study has also been made of the effect of hydrogen, hydrogen peroxide, and potassium iodide on the radiation stability of boric acid solutions.
Date: December 3, 1952
Creator: Hart, Edwin J. (Edwin James), 1910-; McDonell, William R. & Gordon, Sheffield
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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
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Design and Testing of a High-Heat Flux Electron-Bombardment Heater

Description: Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
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Determination of Zirconium and Total Fluoride Ion in Zirconium - Hydrofluoric Acid Solutions

Description: An analytical method has been developed for zirconium and fluoride ions in the system resulting from the dissolution of fuel elements in hydrofluoric acid. The method is based on determination of the density and electrical conductivity of the dissolved metal solution.
Date: February 16, 1953
Creator: Vogler, Seymour; Vogel, Richard C. & Shor, R. W. (Roberta W.)
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Development of a Process to Produce Zirconium Hanford Type Process Tubing by Roll Forming And Inert Arc Welding

Description: The development of methods which were successful in producing zirconium Hanford type process tubing by roll forming and inert are welding (He) flat strip to which appropriate rails had ben previously attached by resistance welding is described in this report. Grade 2 drip arc melted crystal bar material was used.
Date: May 1, 1953
Creator: Noland, R. A. & O'Keefe, G. B.
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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-
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Development of Zirconium Clad Uranium Plates for Reactor Fuel

Description: In this investigation a method has been developed for production of Zrclad uranium plate based upon previous investigations at Argonne and Oak Ridge National Laboratories, and preliminary in investigations in their present work. The present preliminary investigations included experimental studies of the effect of interface atmosphere upon roll bonding and led to the conclusion that thin layers of air between bonding surfaces could be tolerated.
Date: unknown
Creator: Lawless, J. J.; Bean, C. H.; Wooland, J. R. & Macherey, R. E.
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Differential Thermal Analysis of Irradiated Diamond and Silicon Carbide

Description: It was demonstrated by differential thermal analysis (DTA) that: 1. Catastrophic amounts of energy can be stored in diamond. 2. Even at low irradiations, the release takes place over serval hundred degrees, indicating a spectrum of activation energies. 3. At higher irradiations, the stored energy release is considerably less than the increased energy contents and seems not to have been completely released even at the highest temperatures reached. 4. There is some indication of an increased heat… more
Date: December 1, 1954
Creator: Primak, William, 1917-
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Dimensional Stability of Uranium Powder Compacts Upon Thermal Cycling

Description: Thermal cycling tests on uranium have shown that the dimensional changes that occur on cycling in the alpha range are directly related to both the texture of the material and its grain size: cold rolled rods generally elongate in the direction of rolling, while the same rods, after a beta-treatment, grow at rates several orders of magnitude lower. This considerable improvement by beta-treatment has been attributed to the texture randomization accompanying the heat-treatment. In the course of th… more
Date: November 30, 1953
Creator: Mayfield, R. M.; Zegler, S. T. & Chiswik, H. H.
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Dissolution of Uranium Oxide Arising From Slug Failure

Description: The purpose of this work was to study reagents which might be effective in dissolving uranium oxide produced during slug failures in water-cooled reactor systems. An aspect of this problem which has subsequently become of primary importance is the solubility or transportability of the oxide in pure water.
Date: July 1953
Creator: Johnston, F. J.; Wills, P. E. & Katz, Joseph J. (Joseph Jacob), 1912-2008
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