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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.
Partner: UNT Libraries Government Documents Department
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Corrosion of INOR-8 and Inconel Dissolver Components of the Fluoride-Volatility Process

Description: The corrosion of INOR-8 and Inconel dissolver components used in the fluoride volatility process for the dissolution of zirconium with anhydrous HF in molten salts was investigated. Ten dissolution runs were made using simulated subassemblies formed from Zircoloy-2. The dissolver and components were made from INOR-8. Both the dissolver vessel and draft tube were examined several times during the series of runs. The solids which formed at different areas in the system were also analyzed. The res… more
Date: December 30, 1959
Creator: Fink, Frederick W.
Partner: UNT Libraries Government Documents Department
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Rupture Kinetics of Zircaloy-Clad Fuel Elements in High Temperature Water and Steam Interim Report 6 Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanism

Description: This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62… more
Date: December 30, 1959
Creator: Troutner, V. H.
Partner: UNT Libraries Government Documents Department
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Corrosion Resistance of CD4MCu Stainless Steel in Reactor-Related Environments

Description: Because of its good mechanical and fabrication properties, the corrosion resistance of CD4MCu was determined in several solutions under both static and dynamic conditions. It is the purpose of this report to describe the results of these tests.
Date: November 30, 1959
Creator: Hess, D. N.; Greeley, R. S.; Neumann, P. D. & Griess, J. C.
Partner: UNT Libraries Government Documents Department
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The Effects of a Detonation Within a Process Cell

Description: Estimates are made of the effects of a detonation within a process cell. The effects and calculated magnitude of the November 20, 1959 Building 3019 explosion are compared with what is considered to be the maximum credible explosion.
Date: November 30, 1959
Creator: Nichols, J. P.
Partner: UNT Libraries Government Documents Department
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Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly apparent in the analysis of syste… more
Date: November 30, 1959
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Final Technical Report on Physics Research

Description: Results are summarized on theoretical considerations of the excited states of the Ca isotopes, experimental studies of the level structure of Ca42 and Ca44, studies of the production of circularly polarized bremsstrahlung by beta rays, the Moller scattering spectrometer, and the Moller scattering coincidence experiment.
Date: November 30, 1959
Creator: McCullen, J. D.; Kraushaar, J. J.; Woolum, J. C.; Sandifer, C. W.; Kliwer, J. K.; Baker, D. et al.
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959

Description: Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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Leveling of Extraction Tool Crane Rails. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-246, FY-59-323

Description: The purpose of the test was to check the extraction crane rails in the area of the reactor pit for level and parallelism. The west extraction crane rail exceeded the allowed tolerance of 1/32 inch at only one location. The elevation of the north bumper was out of tolerance by 1/64 inch. The east extraction crane rail was consistently lower than the west rail by as much as 8/64 inch. The east rail was parallel with the west rail within allowable tolerances over the length tested except at one lo… more
Date: November 30, 1959
Creator: Pazuchanics, Nicholas
Partner: UNT Libraries Government Documents Department
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MODEL STUDIES OF FLOW AND MIXING IN THE PARTIALLY ENRICHED GAS-COOLED POWER REACTOR

Description: A quarter-scale flow model, using air as a working fluid, was used to obtain design data for the PEGCPR program. A design for the core-support cylinder, to provide optimum mixing and core-flow distribution, was developed, following which experimentul studies of core-flow distribution, mixing of flow from the two inlets, flow patterns in plenum spaces, flow patterns in the thermal- shield-coolant passage, and pressure drops throughout the model were carried out. Results obtained in the model wer… more
Date: November 30, 1959
Creator: Flanigan, L.J.; Whitacre, G.R. & Hazard, H.R.
Partner: UNT Libraries Government Documents Department
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The Origin and Nature of Radioactive Wastes in the Atomic Energy Program

Description: There is great uncertainty in defining the nature of radioactive wastes from power reactor fuel reprocessing since it is not yet possible to say which processing methods will be used. For this reason several approaches to the problem and the wastes associated with each are described here.
Date: November 30, 1959
Creator: Bruce, F. R.
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section III. First Performance. Core I, Seed 1. Test Results DL-S-231, T-612394

Description: The purpose of the test was to determine the radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown following plant power operation. Radiation levels at the survey points in the 1-AC and 10BD Boiler Chambers Enclosures and in the Reactor Container Enclosure indicated that no significant radiation hazards were present approximately 25 minutes after all rods had been inserted. The radiation levels approximately 4 minutes after shutdown at the surve… more
Date: November 30, 1959
Creator: Shramko, John, Jr.
Partner: UNT Libraries Government Documents Department
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SM-2 Critical Experiments : CE-1

Description: Abstract: Critical experiment studies were performed, varying the parameters U235, B10 and metal to water ratio, in the SM-2 7 x 7 core configuration with 38 stationary elements and seven control rods of the SM-1 (APPR-1) type. An experimental mock-up of the SM-1 was assembled using the basic SM-2 fuel plates. Excellent agreement between the SM-1 boron loading, determined by chemical analysis, and the SM-1 mock-up boron loading, for equivalent bank positions, was noted. Several SM-2 mock-ups, … more
Date: November 30, 1959
Creator: Noaks, J. W.; McCool, W. J.; Robinson, R. A.; Schrader, E. W. & Weiss, S. H.
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Partner: UNT Libraries Government Documents Department
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SRE FUEL ELEMENT DAMAGE. Interim Report

Description: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated. A series of fuel element inspections was begun to ascertain the cause of these circumstances, and several fuel elements were discovered to have suffered substantial damage. O… more
Date: November 30, 1959
Creator: Jarett, A.A. ed.
Partner: UNT Libraries Government Documents Department
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Storm Data and Unusual Weather Phenomena, Volume 1, Number 10, October 1959

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: November 30, 1959
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
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The Thermal Expansion of Synthetic Graphites at Temperature Intervals Between 80 and 2000f

Description: The mean linear and cubical coefficients of thermal expansion of eight commercial samples of graphite were determined for temperature intervals between 80 and 2000 deg F. The linear thermal expansion was measured with an automatic recording dilatometer using a rod-shaped specimen 2 in. long and 1/4 in. across. The specimen was heated in an atmosphere of helium. The results were in good agreement with those of Currie, Hamister, and MacPherson. The mean linear coefficient was found to increase wi… more
Date: November 30, 1959
Creator: Allen, R. D.
Partner: UNT Libraries Government Documents Department
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Time Variation of Thermodynamic Parameters of a Gas in the Region of a Shock Front : Progress Report III

Description: The original goal of this investigation was to compare the thermodynamic characteristics of the gases in and behind the shock fronts in gases at initial pressures in the millimeter range and to compare these characteristics in the geometries of single and double discharges. The shock fronts were not visible, so it was not possible, at these pressures, to get visual data from the shock front itself. The parameters giving the properties of the gases were faces. Measurements made with an image con… more
Date: November 30, 1959
Creator: Eastmond, E. John (Elbert John), 1915-; Hales, Richard Wayne, 1926-; Hoyt, G. D.; Baird, Ramon C.; Chowdhury, P. N. R. & Strong, William J
Partner: UNT Libraries Government Documents Department
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Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2

Description: The hydrodynamics code BOCH was used to obtain the relationship between a large number of variables such as voids, flux, pin spacing, power density, and pressure for VMR lattices. Based upon these relationships, a reference core design was selected for examination, using the integrated physics and hydrodynamics analytical modeis. The analog representations of the VMR core kinetics describing the individual blocks of a model block diagram were completed. A simplified core physics analysis was co… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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AIR CORE CRYOGENIC MAGNET COILS FOR FUSION RESEARCH AND HIGH ENERGY NUCLEAR PHYSICIS APPLICATIONS

Description: It is shown that cryogenic techniques offer the possibility of substantially improving the efficiency and practicality of generating high magnetic fields in air-core coils of large size. Over-all reductions in power requirements of as high as 25, by comparison with conventional coils, are predicted, provided high purity conductors and efficient refrigeration cycles are used. (W.D.M.)
Date: October 30, 1959
Creator: Post, R. F. & Taylor, C. E.
Partner: UNT Libraries Government Documents Department
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The Design of Large Cryogenic Magnet Coils : Paper No. 2

Description: Abstract: "Preliminary design and experimental work aimed toward fabrication of large magnet coils with encapsulated sodium conductors is outlined. Aspects of cooling cycles are discussed along with heat transfer, thermal stability, and the mechanical reinforcement of such coils."
Date: October 30, 1959
Creator: Post, Richard F. & Taylor, C. E.
Partner: UNT Libraries Government Documents Department
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