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On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

Description: From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the te… more
Date: December 1966
Creator: Valentin, Richard A.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: November 1965

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: December 27, 1965
Creator: Adams, R. M. & Glassner, A.
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
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
Partner: UNT Libraries Government Documents Department
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Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952

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, 1952
Creator: Argonne National Laboratory. Reactor Engineering Division.
Partner: UNT Libraries Government Documents Department
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Helium Leak Detector Test for Hanford And Savannah River Fuel Slugs

Description: The Helium Leak Detector Test provides a method for detecting the presence of minute holes, cracks, fissures, etc. in the aluminum jackets of Hanford and Savannah River reactor fuel slugs which would allow moisture to penetrate to the uranium during reactor operation.
Date: December 31, 1952
Creator: Barnes, A. H.; Smith, F. A. & Wimunc, E. A.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report [for] October, November, and December, 1952

Description: This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.
Date: December 31, 1952
Creator: Foote, Frank G. & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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-
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Quarterly Report October, November and December, 1956

Description: Methods of producing extremely clean surfaces on rolled Zircaloy-2 strip have been investigated. It has been found that the finer abrasives, 400 mesh or finer, are more effective than coarse types because of their ability to penetrate pits and crevices more readily. Two such cleanings, with an intermediate 35 v/o HNO3-5 v/o HF pickle, resulted in a microscopically clean surface. Ultrasonic inspection of the EBWR fuel plates has been completed during this quarter. Approximately 95% of the plates… more
Date: December 31, 1956
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report July, August, and September, 1957

Description: Development work continued on a fused salt process for the recovery of uranium from zirconium-matrix fuel alloys. The fuel is dissolved in a sodium fluoride-zirconium fluoride melt at 600°C by hydrogen fluoride sparging. The melt is then sparged with fluorine gas which volatilizes the dissolved uranium as the hexafluoride. The final decontamination and purification of the uranium hexafluoride are accomplished by fractional distillation. The testing of graphite as a container material for the hy… more
Date: December 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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The Fabrication of a Plutonium Helix for a Doppler Experiment

Description: A helix constructed of plutonium was made to test the Doppler temperature effect in ZPR-III. The helix, 1 inch in diameter and 6-1/4 inches long, contained 240 grams of delta-phase plutonium alloy encapsulated in titanium tubing. Four plutonium rods were extruded, joined together, and pushed into a titanium tube. This tube was swaged tightly over the plutonium rod, and the assembly was wound into a coil. Electrical leads to the coil were made by swaging copper tubing over the ends of the coil. … more
Date: December 1958
Creator: Dunworth, R. J.; Rhude, H. V. & Kelman, L. R.
Partner: UNT Libraries Government Documents Department
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A laboratory Ivestigation of the Fluorination of Crude Uranium Tertrafluoride

Description: Ore concentrates have been converted directly to crude uranium tetrafluoride by hydrogen reduction and hydrofluorination in fluidized-bed reactors. Small-scale laboratory experiments demonstrated that this process can be extended to the production of crude uranium hexafluoride through fluorination of the uranium tetrafluoride in a fluidized bed. The satisfactory temperature range for the reaction lies between 300°C and 600°C. At 450°C the fluorine utilization is between 50 and 80 per cent. With… more
Date: December 1957
Creator: Sandus, O. & Steunenberg, R. K.
Partner: UNT Libraries Government Documents Department
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