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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.
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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.
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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
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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.
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Reactor Engineering Division Quarterly Report Section I January, February, March. 1956

Description: Physical calculations have been performed 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 two 0.020-in. cladding layers) are to be made of both natural uranium and uranium containing 1.44% U235. Any given fuel assembly contains six identical plates. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated. Various configurations of these fuel assemblies can be used to (1) … more
Date: July 1956
Creator: Members of the Reactor Engineering Division
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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.
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Summary Report of the Hazards of the Internal Exponential Experiment (ZPR-V)

Description: The Internal exponential Exponential Experiment (ZPR-V) will be constructed by loading up to 49 of the fuel cans, containing up to 155 kg of U235, of the present Fast Exponential Experiment in a 22-in. square iron tank, surrounded by an annular thermal region of fully enriched light water lattice 10 to 15 cm thick. This assembly will be placed in a 5-ft diameter tank which will, in turn, be located in the 10-ft diameter ZPR-II tank, the annular space between the outer tanks containing water for… more
Date: March 1956
Creator: Hummel, H. H.; Martens, F. H.; Meneghetti, D.; Bryan, R. H. & Reardon, W. A.
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Reactor Engineering Division Quarterly Report [for] October, November, December 1955. Section I

Description: The gastight steel building (400,000 cu ft) in which all radioactive components are to be housed has been completed by the Graver Tank Company. This structure was tested for strength at 18.75 psig (20% above design pressure) and then tested for leaks. No leaks were found in soap bubble testing of all welded seams. Continuous measurements of temperature and pressure over a ten-day period showed the leakage, if any, to be less than the 500 cu/ ft/day at 15 psig specified. The gastight cylinder wa… more
Date: April 1956
Creator: Members of the Reactor Engineering Division
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ALPR Preliminary Design Study (Argonne Low Power Reactor) Phase 1

Description: A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Enginee… more
Date: April 20, 1956
Creator: Treshow, M.; Pearlman, H.; Rossin, D. & Shaftman, D.
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Environmental Radioactivity at Argonne National Laboratory. Report for the Year 1953

Description: The radioactive content of samples of rain, surface water, soil, plants, and material from the beds of surface waters (bottom silt) which were collected and analyzed during 1953 are given in this report. Samples were collected form the Laboratory site, at locations with 25 miles, and at places 100 miles from the Laboratory. Since Laboratory waste water is discharged into Sawmill Creek, water from the this stream was analyzed daily. Other samples were collected from the Laboratory site periodica… more
Date: July 1954
Creator: Sedlet, J. & Stehney, A. F.
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The Regeneration Factor as a Function of Time in a Th232 - U235 Thermal Reactor

Description: This technical report is concerned with a theoretical investigation of the variation of the regeneration factor [gamma] in a Th232 - U235 thermal reactor. The abundances of the significant isotopes in the thorium-uranium cycle have been derived as a function of irradiation time at constant reactor power. The change in [gamma] as a function of irradiation time at constant power was calculated for combinations of enrichment and resonance escape probability considered likely to exist in a thermal … more
Date: September 1954
Creator: Carter, J. C.
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Testing of Fuel Element Parts and Assemblies by the Radiographic Method

Description: Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be under… more
Date: July 1, 1954
Creator: VanderLaan, Robert H.
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Preliminary Hazard Summary Report on the Boiling Experiment Reactor (BER)

Description: Experiments performed by the Laboratory with the Borax Reactor at the National Reactor Testing Station have demonstrated that a boiling reactor possesses inherent safety characteristics which have not previously been included in the estimation of reactor hazards. Other operating characteristics of Borax were also sufficiently attractive to justify the development of boiling reactors for package power and central station power plant applications. Accordingly, a proposal was made to the Atomic En… more
Date: May 1954
Creator: West, J. M.; Anderson, G. A.; Dietrich, J. R.; Harrer, Joseph M.; Jameson, A. S. & Untermyer, Samuel, 1912-
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Metallurgy Division Quarterly Report January, February, and March 1954

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: March 31, 1954
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
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Chemical Engineering Division Summary Report January, February, and March, 1954

Description: Progress is reported on (1) direct cycle boiling reactor studies, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) fluidization studies, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: May 1, 1954
Creator: Lawroski, Stephen; Rodger, W. A. & Vogel, R. C., 1928-
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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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Soluble Poisons in Reactor Control

Description: Theoretical and experimental investigations of the use of soluble poisons (neutron absorbers) to supplement mechanical control rods are summarized. Experimental evaluation of poisons of interest includes in-pile and out-of-pile tests simulating anticipated reactor operating conditions. Other phases of the investigation included methods of poison injection, removal, and cleanup of poison-diluted reactor systems, as well as studies to evaluate possible application of soluble poison control in exi… more
Date: November 1955
Creator: Breden, Calvin Rudolph, 1901-; Brown, W. S. & Sivetz, M.
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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.
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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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Chemical Engineering Division Summary Report October, November, and December, 1953

Description: Progress is reported on (1) experimental breeder reactor program, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) denitration of uranyl nitrate in a fluidized bed, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: January 1, 1954
Creator: Lawroski, Stephen & Stevenson, C. E.
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Fabrication and Properties of Extruded Silver-Cadmium Control Rods

Description: The production of cross-type control rods having a span of 4-7/8 in., and an arm thickness of 1/8 in., was studied. Extrusion techniques were developed for producing cross-type control rods from each of two alloys; one containing 75% silver-25% cadmium, and the other containing 67% silver-30% cadmium-3% copper. Fabrication of the extruded crosses into clad control rods for the Mark I naval reactor was attempted. A set of unclad control rods for the Zero Power Reactor was produced. The effect of… more
Date: January 1952
Creator: Dwight, Austin E. (Austin Elbert), 1919-
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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.
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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.
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