UNT Libraries Government Documents Department - 54 Matching Results

Search Results

Results: 1 - 24 next
open access

Metallurgy Division Quarterly Report October, November, and December 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: December 31, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 1953

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: December 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Refine your search to only Report
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
open access

Factors Which Affect Formation and Deposition of Transport Corrosion Products in High-Temperature Recirculating Water Loops

Description: Deposits of corrosion products form on heat transfer surfaces and in radiation flux zones at temperatures around 500F in stainless steel systems operating with circulating water. The report considers the possible harmful effects of such deposits on heat transfer and fluid flow, as well as factors involved in the origin of these corrosion products and in the mechanisms of deposition. The prevention of deposition by chemical, mechanical, and electrostatic methods is discussed.
Date: December 1953
Creator: Wohlberg, C. & Kleimola, F. W.
Item Type: Refine your search to only Report
open access

Reactivity as a Function of Irradiation Time in Thermal Reactors

Description: Equations governing the variation of U235. U238, Pu239, Pu240, and Pu241 have been derived and their solutions plotted as a function of irradiation time. The initial U235 content of the uranium was varied from 0.5% to 2.0%. The range of conversion ratios was from 0.5 to 1.2. The irradiation was from 0 to 20,000 mwd/ton of fuel. Since a range of initial conversion ratios is associated with each value of enrichment, a solution results in a family of curves for each isotope, and, since the range o… more
Date: December 1953
Creator: Carter, J. C. & West, J. M.
Item Type: Refine your search to only Report
open access

Roll Cladding of Uranium-Niobium Alloys for Plate Type Fuel Elements

Description: The feasibility of cladding plate type, corrosion resistant uranium-niobium fuel elements with Zircaloy-II by roll bonding has been demonstrated. Plates with cores of uranium alloyed with 3 w/o and 6 w/o Nb intended for irradiation testing in a high temperature water test loop in the MTR have been finished withing specified tolerances. The preparation of cladding billet core and clad components and the assembly of billets by enclosing cores in welded Zircaloy-II jackets can be readily accomplis… more
Date: December 1953
Creator: Bean, C. H. & Macherey, R. E.
Item Type: Refine your search to only Report
open access

Atomic Energy Commission Division of Reactor Development Reactor Information Meeting. Part VI, Processing; October 7, 8, 9, 1953

Description: On October 7, 8, and 9, 1953, the Atomic Energy Commission Division of Reactor Development held a reactor information meeting at the Argonne National Laboratory. The objective of the meeting was exchange of information among people actively concerned with the design of reactors for power to the end that the power reactor program would move more speedily and more economically to another milestone of success. In this volume all the papers presented at the meeting are listed. Copies are given of t… more
Date: October 1953
Creator: Lawroski, Stephen
Item Type: Refine your search to only Report
open access

Eddy Current and Ultrasonic Testing of CP-6 Fuel Elements

Description: The fuel element to be used in the Savannah River reactors is a natural uranium slug 1.00 in. in diameter and 8 in. long, encased in a 2S aluminum can 1.080 in. O.D. having a wall thickness of 0.035 in. The slug is bonded to the can with an aluminum silicon alloy, using the Hanford Al-Si process.
Date: December 1953
Creator: McGonnagle, Warren J. & Doe, W. B.
Item Type: Refine your search to only Report
open access

Metallurgy Division Quarterly Report July, August, and September 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,
Date: September 30, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Item Type: Refine your search to only Report
open access

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
Item Type: Refine your search to only Report
open access

Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs (including the Power Breeder Reactor (PBR) and the Central Station Water Reactor (CSWR)), designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: September 15, 1953
Creator: Argonne National Laboratory. Reactor Enginneering Division.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

The Manufacture of Internal Blanket and Fuel Blanket Slugs for the Experimental Breeder Reactor

Description: Surrounding the core of the Experimental Breeder Reactor (EBR) is located the Internal Blanket (see Figure 2 of Reference 1). This blanket is compromised of natural uranium rods jacketed in stainless steel. The active portion of each rod is made up of five natural uranium slugs 0.873" diameter x 4.050" long. The slugs, stacked one of top of another, are held together and protected by a drawn-on stainless steel tube with welded and closures. These internal blanket rods are located inside the ext… more
Date: December 1953
Creator: Macherey, R. E. & Zegler, S. T.
Item Type: Refine your search to only Report
open access

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
open access

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.
Item Type: Refine your search to only Report
open access

Preferred Orientation in 300 C Rolled and in Recrystallized Uranium Sheet

Description: The rolling and recrystallization textures in 300 C rolled uranium sheet were investigated using a Geiger counter diffractometer with the modified Schulz reflection technique. Seven sections of sheet material were used in order to obtain sufficient data for quantitative pole figures by the reflection technique. A special integrating specimen table was used for obtaining and recording the data atomically.
Date: September 15, 1953
Creator: Mueller, Melvin Henry, 1918-; Knott, Harold W. & Beck, Paul A. (Paul Adams), 1908-
Item Type: Refine your search to only Report
open access

An Improved Continuous Ether Extractor for the Determination of Uranium in Dissolver Solutions

Description: An improved continuous ether extractor is described. The modifications include a means of safely disposing of the active raffinate and a means of positivity checking the raffinate for completeness of uranium extraction. The results obtained on synthetic samples and on dissolver solutions are given. This work was undertaken because of a need for the determination of uranium in dissolver solutions with an accuracy of 0.1 per cent. After a review of available methods it was decided that a gravimet… more
Date: August 27, 1953
Creator: Bane, R. W. & Jensen, K. J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

The Electrolytic Refining of Uranium

Description: This technical report describes work done on the electrolytic refining of natural uranium in fused salt baths composed of various eutectics of alkali metal chlorides in which were dissolved UF, or UCl3.
Date: August 2, 1953
Creator: Marzano, Carlo, 1905- & Noland, N. A.
Item Type: Refine your search to only Report
open access

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
Item Type: Refine your search to only Report
open access

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
open access

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
Item Type: Refine your search to only Report
Back to Top of Screen