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The Thermal Neutron Cross Section Of 9.2h Xe135 : Supplement to Report CP-2782

Description: In this report it reviews a possible declassification of the content of report CP-2782 (February 15, 1945) that presents the data of the most careful measurements of the thermal neutron cross section of 9.2h Xe135 and re-evaluation of the particular methods of measuring neutron flux employed in this experiment had been made for other purposes.
Date: September 12, 1952
Creator: Freedman, Melvin S. (Melvin Sleen), 1915-
Item Type: Refine your search to only Report
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A Capsule Design for Experimental High-Flux Irradiations Of Fuel Materials

Description: New reactors presently in design or construction stages, as well as revised operating procedures for existing reactors, have shown an increasing emphasis on extending the exposure time of the reactor fuel elements. However, operating experience at Hanford, as at other installations, has demonstrated that as the amount of burn-up in uranium metal is increased an increase is also noted in operational difficulties resulting from the dimensional behavior of the fuel. During reactor irradiation uran… more
Date: October 6, 1952
Creator: Kittel, J. Howard & Tedeschi, P.
Item Type: Refine your search to only Report
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Effects of Preferred Orientation and Grain Size On Dimensional Stability of Uranium on Thermal Cycling and Irradiation : Final Report -- Metallurgy Program 5.1.7

Description: The growth of alpha-rolled uranium rods on thermal cycling has been shown to depend on both preferred orientation and grain size. Preferred orientation appears to be a necessary condition for growth to occur; the extent of the growth depends upon the sharpness and type of texture developed and on the grain size. The highest growth rates occur in specimens with highly developed textures coupled with small grain sizes. The growth rates increase with cycling level, particularly in specimens of lar… more
Date: March 1956
Creator: Chiswik, H. H.
Item Type: Refine your search to only Report
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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
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Recovery of Uranium From Ore Concentrates

Description: The use of bromine trifluoride solution has been investigated for the preparation of purified uranium hexafluoride from ore concentrates. The best yields were obtained with the use of antimony pentafluoride solutions in bromine trifluoride, and less fluorine was consumed in the case of previously hydro fluorinated samples. This approach appears to be technologically sound and may prove economically superior to existing procedures in the case of newly constructed facilities.
Date: March 1953
Creator: Sheft, Irving; Hyman, H. H. & Katz, Joseph J. (Joseph Jacob), 1912-2008
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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
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Reactor Engineering Division Quarterly Report : December 1, 1952 Through February 28, 1953

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, research, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: March 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division
Item Type: Refine your search to only Report
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The Use of the Electrical Conductivity of Graphite as a Radiation Damage and Flux Monitor. Implications of the Results to the General Theory of Radiation Damage

Description: A method for monitoring radiation damage irradiations using the change of the electrical conductivity of graphite is described. Results of monitoring operations in a number of locations are given. An attempt is made to explain the damage rate found in the converter at CP-3. An estimate of the flux spectrum in VT-4 and the converter of CP-3 is made and the damage rate is computed according to theories of Seitz and James. It is found that the experimental results are more in accord with the predi… more
Date: July 13, 1953
Creator: Primak, W. L. & Fuchs, L. H.
Item Type: Refine your search to only Report
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Thermal Annealing of Neutron Induced Discomposition in Artificial Graphite : [Part] III, Heating-During-Irradiation Experiments

Description: Experiments are described in which the pile-induced changes in electrical resistivity and elastic modulus of graphite were investigated as functions of the sample temperature during bombardment and the amount of bombardment. The data are for relatively low bombardment times (up to ca. 20 L-units) and temperatures (up to 340*C) and are not sufficiently extensive to permit unequivocal conclusions.
Date: April 13, 1953
Creator: Neubert, T. J.
Item Type: Refine your search to only Report
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The Isolation and Purification of Neptunium-237 Obtained From Hanford Wastes

Description: Through the efforts of the Hanford Engineer Works a quantity of neptunium-237 was separated from uranium waste solutions by a modification of the standard plutonium precipitation process, This material, as concentrates, was shipped to Argonne for final isolation and purification of the neptunium.
Date: May 6, 1953
Creator: Hindman, J. C.; Wehner, Philip, 1917-; Sullivan, J. C. & Cohen, Donald
Item Type: Refine your search to only Report
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Chemical Engineering Division Summary Report : January, February, And March 1953

Description: Dissolution of the large number of samples obtained from the natural uranium blanket of the Experimental Breeder Reactor after approximately 485,000 kw.-hr. of operation has been completed, and analysis of these samples for uranium consumed and plutonium formed is well along. An attempt is being made to distinguish quantitatively between uranium-238 and uranium-235 fission in the blanket area by determining the ratio of ruthenium-106 to cesium-137 in the fission products.
Date: May 12, 1953
Creator: Lawroski, Stephen & Stevenson, C. E.
Item Type: Refine your search to only Report
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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
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Metallurgy Division Quarterly Report [for] October, November, and December 1955

Description: A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the eliminati… more
Date: June 1965
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Item Type: Refine your search to only Report
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Chemical Engineering Division Summary Report

Description: Measurement of radioactive carry-over was made on borax III operating at 300 psig and at power levels ranging from 4 to 14 mv. Decontamination factors of from 1.5 x 104 (at 14 mv) were obtained. These data are in essential agreement with those predicted by previous laboratory experimental work.
Date: May 2, 1956
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
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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
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The Fabrication of Prototype Fuel Elements for the Experimental Boiling Water Reactor and the Experimental Breeder Reactor

Description: The purpose of this program was to develop techniques and methods for producing fuel elements for the Experimental Boiling Water and Experimental Breeder Reactors. Methods for fabricating large tubes, flat plates, and small pins were investigated. The tube and plates contained U-5 w/o Zr-1.5 w/o Nb alloy and were designed for the EBWR. The pins contained U-2 w/o Zr alloy and were designed for the EBR. Cladding and end seal material of Zircaloy-2 was required for the water-cooled EBWR elements. … more
Date: May 1956
Creator: Sawyer, H. F.; Paynton, W. C.; Loewenstein, P. & Corzine, P.
Item Type: Refine your search to only Report
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Quarterly Progress Report on Reactor Development 400 Program

Description: Physics calculations have been made for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates, 0.205 in. and 0.274 in., including the two 0.020-in. cladding layers, are to be made of both natural U and U containing 1.44% U235. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated with six identical plates each. Various configurations of these fuel assemblies will be used to (1) change the critical size of the core,… more
Date: April 30, 1956
Creator: Stuart McLain & Members of the Laboratory Staff
Item Type: Refine your search to only Report
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Chemical Engineering Division Summary Report July, August, and September, 1956

Description: Additional runs have been made in the six-inch, continuous-flow mixing chamber to study the rate of mass transfer between isobutanol and water. These runs were inconclusive because the effluents were mutually saturated. A new four-inch cell has been designed and is being fabricated; this will permit a reduction in the time available for mass transfer. Consideration has been given to other liquid pairs which may transfer more slowly than isobutanol-water. The system nitrobenzene-ethylene glycol … more
Date: December 1956
Creator: Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
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Chemical Engineering Division Summary Report October, November, and December, 1956

Description: A final series of runs was made in a four-inch continuous-flow mixing chamber to study the transfer of isobutanol into water and nitrobenzene into ethylene glycol. Satisfactory techniques were developed to provide for the rapid analysis of these systems. In addition, a light-scattering correlation was prepared to provide a measure of the interfacial area of the yellow-colored nitrobenzene-ethylene glycol mixtures.
Date: March 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
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