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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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Differential Thermal Analysis. Qualitative Study of Nitrate - Butyl Phosphate Systems

Description: Differential thermal analysis has been demonstrated to be a valuable qualitative tool for the study of nitrate-organic reactions. Quantitative data can become available by this method. In tributyl phosphate saturated with nitric acid an exothermic reaction was initiated near 150'C. Nitrate salts were found to be involved in exothermic reactions at higher temperatures usually after an endothermic reaction at lower temperatures.
Date: 1960
Creator: Baldwin, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Comments on the Ioffe Experiment

Description: A recent paper by Ioffe et al. indicates the presence of an additional loss mechanism (other than charge exchange) when a hot plasma is confined in a mirror geometry. It is the purpose of this note to point out that most of Ioffe's measurements fall into a very regular pattern and can be qualitatively explained by the assumption of a single monotonic relation between the unknown loss rate and the average ion energy. A discussion of some possible origins of the addition loss rate is given.
Date: January 22, 1960
Creator: Simon, Albert, 1924-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dependence of Core Power Density on Reactor Parameters in a Gas-Cooled Reactor

Description: The influences of various key parameters on the reactor average core power density of gas cooled reactors are not easily seen from inspection of general analytic equations because of the interdependence of many key variables. A method is presented by which the analytical expression is reduced to a simple, approximate relation expressing the core power density as a function of independent key parameters of limited range.
Date: January 27, 1960
Creator: Ozisik, M. Necati & Korsemeyer, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Protection of Space Vehicles From Meteorite Penetration

Description: Thin bumpers have been proposed as a means of protecting a space vehicle from penetration by meteorites. Equations for the determination of the bumper thickness, the minimum spacing from the vehicle, the bumper temperature and the effect of the bumper on the thermal performance of a space radiator have been developed as functions of the duration of space flight, the surface area, temperature and wall thickness of the vehicle, and the physical properties of the bumper and vehicle wall materials.… more
Date: January 20, 1960
Creator: Hefner, R. J. & Lafyatis, P. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thorium Breeder Reactor Study: Optimization of a Blanket Processing Cycle To Obtain Minimum Total Inventory in a Chemical Reprocessing Cycle

Description: A reactor which produces U233 from Th232 needs to operate with as low total inventory of fissionable and potential fissionable material, U233 and Pa233, as possible in order to achieve short doubling times. The blanket processing cycle can be optimized to give minimum total inventory by the proper arrangement of Pa233 decay and U233 extraction steps. The optimization consists in choosing the proper storage time associated with each processing step. Graphs are presented correlating the optimized… more
Date: January 21, 1960
Creator: Carter, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Activated Charcoal Fission Gas Adsorbers Designed for the GC-ORR Loop Experiment No. 1

Description: The activated charcoal traps designed for the Gas-Cooled Oak Ridge Research Reactor Loop Experiment No. 1 are evaluated for room temperature operation involving the decontamination and atmospheric disposal of helium coolant gas contaminated by experiment failure. The maximum quantity of fission products expected to be released was calculated and the resulting hazard was examined on the basis of probable radiation doses to laboratory personnel resulting from exposure to the gas cloud.
Date: January 14, 1960
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplementary Report No. 1

Description: During the investigation of various vacuum problems observations are occasionally made which have no direct bearing on a particular problem but appear to be of sufficient interest to warrant reporting. A number of such observations made over the past several months are summarized in this report.
Date: January 6, 1960
Creator: Normand, C. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposed Modifications to HRE-2 Core

Description: As a result of flow tests of a full-scale HRT flow model, it is proposed to modify the core flow by removing 5 or more screens, plugging the hole and reversing the direction of flow. This will provide better cooling and mechanical scrubbing of the core wall. A procedure for flushing solids out of the core was developed.
Date: January 12, 1960
Creator: Lawson, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modification of a Bausch & Lomb Spectronic 20 Colorimeter-Spectrophotometer For In-Line Applications

Description: A Bausch & Lomb Spectronic 20 Colorimeter-Spectrophotometer has been modified for in-line flow applications. Modifications included redesigned electronic circuitry to provide a DC output signal for recording purposes together with various mechanical changes to accommodate the flow cells.
Date: December 29, 1959
Creator: Gayle, T. M. (Tom M.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry of Pu(IV) Polymer

Description: Pu(IV) polymer may form in solutions containing as much as 0.3 M acid at room temperature. At higher temperatures polymer may be formed at even higher acidities. Dilution of plutonium solutions with water can result in polymer formation due to local dilution of the acid even when the final equilibrated solution would be stable. The polymer may be destroyed in acid solutions by oxidation or reduction of the plutonium or by use of complexing agents.
Date: December 30, 1959
Creator: Rainey, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Control By Addition Of Neutron Poisons To Slurry Reactors

Description: Calculations show that slurry fueled reactors may be maintained subcritical at arbitrary concentrations and at reactor temperatures above a specified minimum by addition of a soluble neutron poison to the slurry.
Date: December 22, 1959
Creator: Pearson, R. L.; Prince, B. E.; Jeffrey, D. W. & Brassert, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Molten-Salt Breeder Reactors

Description: The problems involved in building a molten-salt thermal-breeder reactor are reviewed, and it is concluded that the most feasible construction is an externally-cooled reactor with the fuel salt passing through the reactor core in graphite tubes.
Date: January 12, 1960
Creator: MacPherson, H. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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UO2 Fuel Cluster Study

Description: The reactor physics aspects of a number of different UO2 cluster geometries were determined as a function of various parameters. These parameters included number of rods in cluster, cladding materials, cladding thickness, cored and uncored rods, lattice pitch, rod size, and inter-rod spacing. Lifetime calculations were made on the basis of batch loading and uniform exposure for 5000 and 7500 Mwd/MT-UO2.
Date: December 31, 1959
Creator: Delene, J. G. & Row, T. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Neutron Fluxes in HRE-2 Determined From Zircaloy-2 Induced ActivityMeasurements, Runs 16 and 17

Description: Thermal neutron fluxes prevailing near some Zircaloy-2 specimens exposed during HRT run 17, and near others exposed during runs 17, 16, 14 and 13 have been determined from measurements of the induced activity in the specimens. The neutron fluxes were calculated for an average core power level of 2 Mv.
Date: December 18, 1959
Creator: Baker, J. E.; Jenks, G. H. (Glenn Herbert), 1916- & Olsen, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report December 1959 - Chemical Technology Division

Description: Progress is reported on several projects: Druhm, fission product recovery by solvent extraction, fuel cycle development, OCR coolant purification studies, ion exchange, power reactor fuel processing and waste processing.
Date: March 3, 1960
Creator: Bresee, J. C.; Blomeke, J. O.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Watson, C. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Problem Statement - Treatment of Declad Wastes for Disposal

Description: It is proposed that decladding wastes be converted to dry solid "packages" suitable for ultimate storage in a dry environment. Low temperature solidification of Sulfex and Zirflex decladding wastes by addition of lime, plaster of paris, portland cement, drying agents, etc. seems feasible. A similar treatment of Darex decladding wastes probably should be preceded by chloride removal and nitrate destruction. Calcination may be a preferable alternative for Darex wastes.
Date: December 15, 1959
Creator: Roberts, J. T. & Tomlin, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Description of a Proposed Program: Dynamic Analysis of Radiochemical Plant Components

Description: A study is proposed to analyze the solvent extraction operation in order to produce a method of calculating steady state contactor performance for optimizing new flow sheets, and to describe the transient effects in the operation in order to better understand the limitations of the steady state model, to establish quantitative criteria for control, and to provide models for future application to computer controlled plants.
Date: December 15, 1959
Creator: Whatley, M. E. (Marvin E.), 1926-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Economic Effects of Gas-Cooled Reactor Parameters

Description: The economic effects of varying key reactor design parameters are examined for the case of a graphite-moderated helium-cooled reactor with stainless-steel-clad UO2 fuel elements. Other variables studied are the number of fuel rods per fuel cluster, the fuel volume fraction, fuel inventory charge, and the pressure vessel wall thickness.
Date: December 9, 1959
Creator: Perry, Alfred M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium-Thorium Separation By Di-Sec-Butylphenylphosphonate Extraction

Description: On the basis of data reported here and data reported in ORNL-CF 59-11-25, it is believed that the given process is feasible for high purification of the U-233 products with respect to thorium (Th-232 and Th-228) contaminants. Further tests with the actual pilot plant product solutions (and/or with spikes thereof) appear to be indicated if it is desirable to demonstrate thorium DF's greater than 10<sup>2.
Date: December 9, 1959
Creator: Gresky, A. T. & Mansfield, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation Of The Diffusion Coefficient Of Pertechnetate And Perrhenate Ions From Conductivity Measurements

Description: In order to calculate the number of electrons involved in the polarographic reduction process by means of the Ilkovic equation the diffusion coefficient must be known. Therefore specific conductance measurements of KReO4 and KTcO4 solutions were made. From these data the diffusion coefficient of ReO4 and TcO4 ions were calculated.
Date: December 9, 1959
Creator: Thomason, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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