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Calculated Thermal Ionization And Enthalpy of Hydrogen, Nitrogen, And Argon At One Atmosphere Pressure In The 298-20, 000'K Temperature Range

Description: The degree of dissociation and ionization and the enthalpies of hydrogen and nitrogen, and the degree of ionization and the enthalpy of argon are calculated for one atmosphere pressure and temperatures up to 20,000'K. All three gases are more than 93% ionized at 20,000'K, and have enthalpies ranging from 553 kcals for argon to 1074 and 1225 kcals, respectively, for hydrogen and nitrogen.
Date: September 15, 1960
Creator: Bond, Walter Dayton
Partner: UNT Libraries Government Documents Department
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Progress Report for February-March 1961 - Chemical Development Section C, Chemical Technology Division

Description: This report summarizes certain activities by the Oak Ridge National Laboratory's Chemical Technology Division, which focused on chemical separation processes relevant to nuclear fuel reprocessing, from February to March 1961. It includes data from experiments exploring the recovery of thorium and uranium from granitic rock, fission product (cesium) recovery, final cycle plutonium recovery by amine extraction, and the separation of transplutoniums from lanthanides.
Date: August 15, 1961
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
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Preprocessing of Procedure in the ORACLE-Algol Translator

Description: This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on th… more
Date: May 15, 1961
Creator: Bumgarner, L. L.
Partner: UNT Libraries Government Documents Department
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Nuclear Characteristics of BeO-Moderated Cores vs Graphite-Moderated Cores

Description: Multigroup calculations were performed to compare BeO-moderated cores, using various void fractions and core diameters. The core leakages and conversion ratios which were calculated are presented in a series of curves.
Date: January 15, 1960
Creator: Carlsmith, R. S.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor - A General Description

Description: This report is issued primarily to make available a general description which reflects the current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge National Laboratory.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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Disassembly and Postoperative Examination of the Aircraft Reactor Experiment

Description: The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much… more
Date: April 15, 1958
Creator: Cottrell, W. B.; Crabtree, T. E.; Davis, A. L. & Piper, W. G.
Partner: UNT Libraries Government Documents Department
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The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process

Description: Results of tracer studies suggest that, in tributyl phosphate extraction processes designed to recover and purify fissionable material, minimum ruthenium extraction should be obtained from feeds at least 2 M in nitric acid or at least 1 M acid-deficient. Ruthenium decontamination was decreased by preheating the feed and increased by pretreatment with reducing agents. A pretreatment using 0.06 M ferrous ion and 0.5 M urea with 1 hr simmering at 85°C should increase ruthenium decontamination abou… more
Date: December 15, 1954
Creator: Flanary, J. R. & Frashier, L. D.
Partner: UNT Libraries Government Documents Department
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Containment Properties of DCX

Description: The "absolute" containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confinement in space and momentum are plotted for 300 Kev deuterons.
Date: June 15, 1959
Creator: Fowler, T. K. & Rankin, M.
Partner: UNT Libraries Government Documents Department
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Results of Differential Bed Study of the Kinetics of the Absorption of UF6 on Sodium Fluoride

Description: One step in the Volatility process for power reactor fuel reprocessing involves the absorption and subsequent desorption of UF6 from NaF pellets in fixed beds. In 1958 an experimental study of the kinetics of absorption of HF on NaF beds was made. The purpose of this work was to extend the study to the kinetics of UF6 absorption on NaF. The results should be useful in the design and operation of the Volatility process.
Date: January 15, 1960
Creator: Groves, F. R.
Partner: UNT Libraries Government Documents Department
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Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe

Description: A mathematical model is presented for the prediction of heat transfer coefficients for fully developed turbulent flow of fluids in circular pipes by analogy to the transfer of momentum. There is also presented an empirical velocity distribution equation derived from existing experimental data for use in the analogy model. Heat transfer coefficients for fluids with Prandtl numbers ranging from 0.01 to 100 and Reynolds numbers ranging from 5x10^3 to 10^7 are presented in tabular and graphical for… more
Date: September 15, 1960
Creator: Hefner, R. J.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
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Examination of 6" Diameter "O" Ring from HRT Mockup. Metallography Report (Y-12) No. 39

Description: A six-inch diameter "O" ring from the HRT Mockup was examined metallographically after 2452 hours exposure to uranyl sulfate solution at 300C. surface defects, except for cold work defects were found only in areas exposed to uranyl sulfates. Defects found were pits, transgranular cracks, surface cracks, and grain attacks.
Date: January 15, 1957
Creator: Kegley, T. M., Jr.
Partner: UNT Libraries Government Documents Department
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Oak Ridge National Laboratory Target Preparation Program

Description: In early 1961 a Target Fabrication Center was established at Oak Ridge National Laboratory to carry out the routine preparation of a wide variety of targets and to provide research and development support to the target program. Although most of the effort concerned enriched stable isotopes, both normal and radioactive materials are also handled. With the aid of rolling mills, resistance-heat and electron-bombardment vacuum evaporation, presses, and electroplating equipment, targets of elements … more
Date: January 15, 1963
Creator: Kobisk , E. H
Partner: UNT Libraries Government Documents Department
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The Reaction Between Hydrogen and Oxygen by Catalysis and the Thermal Reaction

Description: From abstract: "The reaction between hydrogen and oxygen with the aid of various catalysts (especially platinum on aluminua) has been studied, and the operating variables such as flow rates, space velocity, temperature, and gas composition have been examined rather extensively. It has been found that hydrogen and oxygen in stoichiometric proportions and mixed with either steam or helium may be made to react to the extent of 99.5% or greater at space velocities up to 30,000 hr-1, or even higher,… more
Date: January 15, 1952
Creator: Kuhn, D. W.; Ryon, A. D.; Palko, A. A. & Clewett, G. H.
Partner: UNT Libraries Government Documents Department
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CANE Sequenced Sampler for Project Gnome: Design Proposal

Description: A design is proposed for sampling apparatus to draw a sequence of samples from a filtered gas stream from a contained explosion. The apparatus is to be designed, fabricated, and installed in Project Gnome under the ORNL CANE Problem.
Date: March 15, 1961
Creator: Landry, J.W.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
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Electromagnetic Research Division Quarterly Progress Report: Part I for Period Ending December 31, 1951

Description: From abstract: "Operation of the 86-inch cyclotron has been continuous except for a three-day interruption caused by a water leak inside the vacuum chamber; monthly output has averaged over 210,000 [mu]a-hr; the average continuous (168-hour week) beam power has been approximately 5.5 kw; and the energy of the beam has been determined to be ~19.4 Mev. No changes due to radiation damage have been detected in Inconel tubes containing UF4-NaF-KF eutectic which were irradited in the 96-inch cyclotro… more
Date: January 15, 1952
Creator: Livingston, Robert S. & Howard, F. T.
Partner: UNT Libraries Government Documents Department
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PRFR Pilot Plant: An Evaluation of Equipment Performance During the Processing of Irradiated Natural Uranium in April 1959

Description: The Power Reactor Fuel Reprocessing complex and the equipment performance during the processing of irradiated natural uranium fuel are described. Equipment performance was generally satisfactory for rates up to 400 kg or uranium per day. =Three cases in which equipment malfunctioning significantly affected the process, and the scheduled modifications, are discussed.
Date: September 15, 1959
Creator: Matherne, J. L.
Partner: UNT Libraries Government Documents Department
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Status Report of the Soluble Poison Shim Control for the HFIR

Description: A number of chemicals have been investigated for their possible use as a soluble poison for the HFIR shim control. A preliminary flowchart was drawn and some heat generation calculations in Zircaloy-2 and boric acid poison solution were made.
Date: December 15, 1959
Creator: McLain, H. I.
Partner: UNT Libraries Government Documents Department
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