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Correlation of Liquid Fraction in Two-Phase Flow With Application to Liquid Metals

Description: A generalized correlation for the liquid fraction in twophase flow is presented which is proposed for use with all iluids, including liquid metals. The correlation is based on isothermal, two-phase, two-component liquid fraction data for liquid Hg--N/sub 2/ and water-air. Liquid fraction is shown to be a function of the Martinelli flow modulus and liquid/gas density and viscosity ratios. Good correspondence is indicated between the liquid fraction predicted by this correlation and the Martinell… more
Date: April 15, 1963
Creator: Baroczy, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydraulic Characteristics of HNPF 8-Rod Fuel Element

Description: Pressure drop and vibration characteristics were determined for an 8-rod fuel element model of the design intended for use with uranium carbide (UC) in the Hallam Nuclear Power Facility (HNPF). Measurements with water as the test fluid were converted to equivalent values for sodium, the HNPF coolant, using the principles of dimensional similitude. Initially UC elements will be concluded in an HNPF core loading comprised primarily of 19-rod U-Mo fuel elements. In this core loading, the UC fuel e… more
Date: August 15, 1963
Creator: Begley, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRODUCTION OF STRONTIUM-TITANATE RADIOISOTOPE FUEL FOR SNAP 7B THERMOELECTRIC GENERATOR

Description: The conversion of strontium-90 to strontium titanate heat source pellets is described. Encapsulation of the fuel in Hastelloy C containers and necessary leak testing, decontamination and calorimetry procedures are covered. Loading of the SNAP 7B thermoelectric generator was accomplished. (auth)
Date: April 15, 1963
Creator: Bloom, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHARACTERISTICS OF A THERMIONIC CONVERTER WITH A HIGH-TEMPERATURE COLLECTOR

Description: Current-voltage characteristics of a cesium-on-tantalum thermionic converter with a collector temperature comparable to that of the emitter were obtained for a variety of electrode temperatures and cesium vapor pressures. The results show that for emitter temperatures in excess of 2000 deg K, power outputs of a few watts per square centimeter can be obtained when the ratio of collector temperature to emitter temperature is as high as 0.75 to 0.80, which is the required range for best performanc… more
Date: January 15, 1963
Creator: Blue, E. & Ingold, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mixtures of Metals With Molten Salts

Description: A review is presented of various types of solutions of metals in molten salts, especially in their own molten halides. With relatively little reference to the older literature, the progress made in the last 20 years is discussed. Roughly, the solutions are classified into two groups: The metal may retain, to some degree, its metallic properties in the solution, or it may lose them through strong interaction with the salt solvent. The alkali-metal systems are typical examples of the former type,… more
Date: August 15, 1963
Creator: Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the Metal Assembly

Description: Information required to obtain authorization to receive and use a fast critical assembly for operation with the General Atomic linear accelerator is documented. The analysis offers evidence showing that operation of the assembly will create no undue risk to the health and safety of the public or the personnel of the Laboratory. Experiments with the accelerator pulsed fast assembly will consist primarily of measurements of neutron yield and pulse shape produced by the electron pulses from the Li… more
Date: August 15, 1963
Creator: Brown, J. R. & Russell, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of impulsively loaded pressure vessels

Description: Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight con… more
Date: October 15, 1963
Creator: Brown, N.; Cornwell, R.; Hanner, D.; Leichter, H. & Mohr, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AN INFORMATION STORAGE AND RETRIEVAL SYSTEM FOR IRRADIATION EFFECTS IN METALS

Description: An information storage and retrieval system (PIC) was developed, utilizing the IBM 7090 computer, for handling data pertaining to the effects of neutron irradiation on metals. The input includes a reference identification, an appropriate abstract or extract summarizing the article, code identification parameters analogous to those used by the ASM-SLA Literature Classification System, and special codes identifying relevant irradiation and testing parameters. The output contains the same data plu… more
Date: August 15, 1963
Creator: Bush, S. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Statistical Treatment of Hot Channel Factors for Compact Reactors

Description: The theoretical development, statistical treatment, and application of hot channel factors in compact SNAP reactors as represented by the SNAP 8 experimental core loading are presented. The channel and rod power effects of variation in the concentrations of uranium, hydrogen, and poison in the fuel rods are given. The statistical distributions of all variables are examined. A random selection of rods and channels is compared to the actual SNAP 8 configuration, with no difference noted. Confiden… more
Date: July 15, 1963
Creator: Cohn, P. D. & Evans, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE DEVELOPMENT OF URANIUM CARBIDE AS A NUCLEAR FUEL. Third Annual Report, September 1, 1961 to October 31, 1962

Description: = 9 6 < ? < 0 t and fabrication method on irradiation stability, thermal conductivity, and hot hardness of uranium carbide were determined. Hypostoichiometric and stoichiometric uranium carbides prepared by both powder metallurgy and skull casting and hyperstoichiometric cast carbide were tested. The preparation of 12% enriched uranium carbide specimens for irradiation testing was completed. Sintered specimens were 98% of theoretical density for hypostoichiometric uranium carbide and 92 to 93% … more
Date: January 15, 1963
Creator: Crane, J.; Kalish, H. S. & Litton, F. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of salt velocity technique

Description: The salt velocity technique for measuring coolant flow through a SNAP 8 tri-cusp channel was studied and developed. The parameters important in obtaining reproducible data were investigated and a test procedure, which yields dath of good precision, was developed. Dath were taken on a tri-cusp channel with flush circular electrodes (0.125 inch O.D.) as well as on a tri-cusp channel with parallel plate electrodes (0.006 inches thick, 0.250 inches long), which were situated 0.050 inches apart and … more
Date: November 15, 1963
Creator: Daleas, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor instrumentation and safety circuit status review and program document

Description: This document has been prepared for internal use by the General Electric Company to serve as a program for evaluating reactor instrumentation and safety circuit equipment needs. It is intended that this document be used as a guide for defining, planning and scheduling engineering effort; budgeting of capital money; and project planning for new instrumentation systems. Effort will be made to periodically evaluate the status of the programs presented and provide updating information accordingly.A… more
Date: February 15, 1963
Creator: Deichman, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A 23-Group Neutron Thermalization Cross Section Library

Description: A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)
Date: July 15, 1963
Creator: Doctor, R. D. & Boling, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process design scope criteria Purex multipurpose dissolvers

Description: An engineering study was recently performed by Separations Process Design Engineering to determine the feasibility of processing the total Chemical Processing Department production load in the Purex Plant. This document summarizes the results of the study and the basis for the scope design or the multipurpose dissolvers for the Purex Plant.
Date: October 15, 1963
Creator: Ehrlich, R. D. & LaRiviere, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Alloying Constituents on Aluminum Dissolution Rates

Description: In studies of the effect of alloying elements on the rate of dissolution of Al in mercury-catalyzed nitric acid, it was observed that Co, Ni, and Si present at concentrations of 1 to 2% have significant passivating effects. Fe was slightly catalytic. Passivation due to Si was partly overcome by contacting the passive alloy with active, high-purity Al. Increased catalyst concentration improved the rates when Ni and Si were present. Neither approach was effective when Cu was the passivating eleme… more
Date: April 15, 1963
Creator: Fletcher, R. D.; Jacobson, M. E. & Beard, H. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LABORATORY DEVELOPMENT OF A COMBINED CHLORIDE VOLATILITY-AQUEOUS PROCESSING METHOD FOR URANIUM-ZIRCONIUM NUCLEAR FUELS

Description: The operations in a process proposed for recovering uranium from spent uranium-- zirconium alloy fuels, including collecting the volatilized chlorination products (mainiy zirconium tetrachioride and uranium pentachloride) in boiling water, concentrating the resulting solution, lowering the freezing point by removing chloride with hydrogen peroxide, and recovering uranium from the 5 M Zr product solution by solvent extraction with tributyl phosphate in Amsco diluent, were investigated in the lab… more
Date: October 15, 1963
Creator: Gens, T.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scope of Chemical Explosive Cratering Experiment

Description: A general description is given of the Pre-Buggy chemical explosive experiments. These experiments consisted of a series of single- and multiple- charge detonations designed to refine our knowledge of channel size as a function of charge spacing, and to obtain data on venting of explosion products from a row of spherical charges detonated in alluvium. A basic series of six single-charge detonations and four multiple-charge detonations of five charges in a row was executed in Area 5 of the Nevada… more
Date: May 15, 1963
Creator: Graves, E.; Wray, W. R. & Pierce, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: January 1963

Description: This document details activities of the irradiation processing department during the month of January, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.
Date: February 15, 1963
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: October 1963

Description: This document details activities of the irradiation processing department during the month of October, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.
Date: November 15, 1963
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OXYGEN-17 NMR SHIFTS CAUSED BY Cr$sup ++$ IN AQUEOUS SOLUTIONS

Description: Cr{sup++} in solution produces a paramagnetic shift in the NMR absorption of 0{sup17} in C1O{sub4}{sup-}, as well as the expected paramagnetic shift for 0{sup17} in H{sub2}O. As the concentration of C1O{sub4}{sup-} increases, the shift in the H{sub2}O{sup17} absorption is diminished, and eventually changes sign. The effects are ascribed to preferential replacement by C1O{sub4}{sup-} of water molecules from the axial positions in the first coordination sphere about Gr{sup++}.
Date: February 15, 1963
Creator: Jackson, J.A.; Lemons, J.F. & Taube, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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