Technical Report Archive & Image Library (TRAIL) - 167 Matching Results

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Reactor Engineering Division Semiannual Report December 1, 1951 through May 31, 1952

Description: This report describes the construction of a reactor and the research conducted in the reactor such as solid fuel and liquid fuel research, boiling reactor experiments, CP-6 bond testing program, and water quality control experiments for CP-6 program.
Date: June 15, 1952
Creator: Members of the Reactor Engineering Division
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Half-Life of Pu241

Description: This report describes the first estimation of the beta half-life of Pu241 and was made by determining the beta activity associated with plutonium formed by (d,xn) reactions on U258.
Date: December 1953
Creator: Mech, Joseph & Pyle, Gray
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Meteorological Data Taken at Argonne National Laboratory, Du Page County, Illinois, July 1951 Through June 1952

Description: The report is the third in a series of interim reports on the climatological studies which are being conducted at the Argonne National Laboratory. First report appeared as document ANL-4538 and covered the period July, 1949 through June, 1950; the second report, ANL-4793, covered the period July, 1950 through June, 1951. These annual reports are offered for purposes of information only; broad conclusions regarding the climate of this site must await the accumulation of a statistically significa… more
Date: February 1953
Creator: Argonne National Laboratory. Radiological Physics Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
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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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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A Summary and Bibliography of Some Research on Radiation Damage in Ceramic Materials Performed at the Argonne National Laboratory

Description: The susceptibleness of certain "ceramic" substances to extreme radiation damage (such as that observed in graphite) as indicated by changes in dimensions and heat content is discussed in terms of the experimental evidence which is available.
Date: March 4, 1953
Creator: Primak, William, 1917-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
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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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
Partner: UNT Libraries Government Documents Department
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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
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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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Progress Report on the Experimental Breeder Reactor April 1, 1951 Through January 31, 1953

Description: This report describes the progress on the experimental breeder reactor. It focuses on the approach to critical experiments, calibration of controls and flues and flux distributions.
Date: February 20, 1953
Creator: Lichtenberger, H. V.; Novick, M.; Cerutti, B. C.; Cameron, R. A.; McGinnis, D. F.; Pettitt, E. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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