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Mercury Amalgam Bonding of Uranium and Copper

Description: Technical report summarizing one phase of work done to develop methods of bonding uranium to a metal which is a good conductor of heat. Silver was chosen for contact with uranium because it is easy to plate on uranium and there is no danger of brittle Ag-U compounds being formed at elevated temperatures. [From Abstract]
Date: January 22, 1951
Creator: Glasgow, L. G.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending April 30, 1952

Description: This quarterly progress report discusses ongoing work at the Metallurgy Division at the Oak Ridge National Laboratory. Topics discussed include thorium research, the preferred orientation of uranium, studies in the ceramics laboratory, the homogenous reactor program, studies in the x-ray laboratory, studies in the metallographic laboratory, the experimental plate-cladding program, and fuel and control element fabrication.
Date: September 22, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridge, W. H.
Partner: UNT Libraries Government Documents Department
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Radiation Stability Studies

Description: From abstract: "An investigation of the radiation stabilities of aqueous solutions of sodium ethylenediamine tetraacetate and sodium acetate was made using a 3000-curie Co⁶⁰ source...A study of the behavior of the standard-size Beckman type glass pH electrodes in a solution containing 0.36 curie of Ce¹⁴⁴-Pr¹⁴⁴ activity per milliliter showed the useful electrode life to be of the order of two to eight days."
Date: September 22, 1952
Creator: Blanco, R. E.; Kibbey, A. H. & Pannell, J. H.
Partner: UNT Libraries Government Documents Department
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The Influence of End Mirrors, High Density and Long Tube Length on Radial Diffusion

Description: Diffusion in an arc plasma across a magnetic field is investigated. The geometry is similar to that reported in ORNL-1890 but with the addition of magnetic mirrors on the ends of the arc chamber. It is shown that mirrors do not eliminate the "short circuit" effect. Comparison of the e-folding length, rₒ, of the radial ion density with and without mirrors, affords a direct measurement of ℓ/λ where ℓ is the arc length and λ the mean-free-path. In addition rₒ is independent of gas pressure with mi… more
Date: September 22, 1955
Creator: Simon, Albert
Partner: UNT Libraries Government Documents Department
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Determination of Trivalent Uranium with Methylene Blue

Description: A direct titrimetric method for the determination of trivalent uranium in uranium trifluoride and mixtures of fused fluoride salts was developed. The method is based on the stoichiometric oxidation of trivalent uranium to the tetravalent oxidation state with an acidic solution of methylene blue. The sample containing trivalent uranium is dissolved at room temperature in an excess of standard methylene blue solution in a carbon dioxide atmosphere; the excess oxidant is variation of the method is… more
Date: November 22, 1955
Creator: Ross, W. J.; Meyer, A. S.; White, J. C.; Kelley, N. T. & Susano, C. D.
Partner: UNT Libraries Government Documents Department
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HRT Sampler Development

Description: A prototype sampler for obtaining samples of high radioactive UO2SO4 solution for use in the HRT is presented. It was successfully operated in conjunction with a low pressure water system and a high pressure, high temperature UO2SO4 system.
Date: January 22, 1957
Creator: Hannaford, B. A.
Partner: UNT Libraries Government Documents Department
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In-Reactor Autoclave Corrosion Studies II : Autoclave Z-19

Description: In order to test the effect of chromate ion on the corrosion of Zircaloy-2 a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm Cr (VI) was autoclaved with rocking at 280 C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the a rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (… more
Date: March 22, 1957
Creator: Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Partner: UNT Libraries Government Documents Department
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In-Reactor Autoclave Corrosion Studies. II, Autoclave Z18

Description: In order to test the effect of chromate ion on the corrosion of Zircaloy-2, a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm of Cr (VI) was autoclaved with rocking at 280 degrees C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presen… more
Date: March 22, 1957
Creator: Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Partner: UNT Libraries Government Documents Department
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The Choice in Thorium Oxide Slurries for the Prevention of Caking in Circulating Systems

Description: A qualitative theory for cake formation in ThO2 slurries is presented. The sphere formation which occurs in "Standard" slurry can be explained on the same basis. The irregular and unpredictable yield strength is easily fitted into the theory. On the basis of this theory, the writer has been led to the conclusion that only colloidally stable slurries, or slurries with crystallites or comminution-resistant particles which are large enough to overcome colloidal effects (probably larger than 0.1u) … more
Date: April 22, 1957
Creator: Lyon, R. N.
Partner: UNT Libraries Government Documents Department
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Deflection Equations for Various Loading of Circular-Arc Curved Beams

Description: In analyzing stresses, deflections, and forces in piping and certain structural systems, it is useful to have a set of equations giving the deflections at any point of a curved beam in terms of the various loads acting on the beam. This technical report presents the deflection equations for a curved circular-arc beam of variable length. The cases treated include in-plane and out-of-plane bending due to forces and moments applied to the end of the beam in three principal directions, and uniforml… more
Date: April 22, 1957
Creator: Platus, D. L. & Greenstreet, B. L.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: November 1956-January 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress of the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: April 22, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
Partner: UNT Libraries Government Documents Department
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In-Reactor Autoclave Corrosion Studies : LITR I. Outline of Methods and Procedures

Description: During the development of in-reactor corrosion experiments three types of bomb designs have been developed for following quantitatively the consumption of oxygen in a bomb which is fabricated from the particular metal under test. The bombs are designed so as to be rocked continuously during their in-reactor exposure, consequently agitating the uranium salt solution contained in the bomb and permitting gentle movement of the solution past metal specimens and other corroding surfaces. The oxygen … more
Date: May 22, 1957
Creator: Warren, K. S. & Davis, R. J.
Partner: UNT Libraries Government Documents Department
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Summary of Corrosion Data for HRT Mockup Operational Period Ending November 5, 1956

Description: The operation of the HRT mockup was on 0.042m UO2SO4, 0.024m H2SO4, and 0.005m CuSO4 at 280 C and 1400 psi pressure. with the O2 content at near 500 ppm. The pump showed bearing wear and high corrosion. The letdown heat exchanger was removed from the mockup and sectioned. The metallographic examination revealed corrosion. Results of corrosion runs on Ti, zircaloy-2, and stainless steel are given.
Date: May 22, 1957
Creator: Wacker, R. E. & Griess, J. C.
Partner: UNT Libraries Government Documents Department
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Supplement to: Curve Plotting Routine for the Oracle (57-4-56)

Description: A general program has been written to plot curves on the Oracle curve plotter. The supplement includes changes to slow down some of the loops and minimize the possibility of read-around errors and changes to handle special cases.
Date: October 22, 1957
Creator: Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on 2% U235-Enriched UF4-C25H52 Critical Assemblies

Description: A series of critical experiments with blocks of 2% U235-enriched UF4-C25H52 has been initiated at the ORNL Critical Experiments Facility. Thus far assemblies with H:U235 atomic ratios of 195 and 294 have been built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres have been determined to be 16.3 and 8.5 kg of U235 for fuel mixtures with H:U235 atomic ratios of 195 and 294, respectively. Th… more
Date: April 22, 1959
Creator: Mihalczo, J. T.; Lynn, J.J.; Scott, Dunlap & Connolly, W. C.
Partner: UNT Libraries Government Documents Department
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Report of Fire in Laboratory Hood, Wing I, Building 4500

Description: The fire involved approximately 30 liters of isopropyl alcohol as a result of the ignition of about 16-18 liters of isopropyl alcohol and a slurry of thoria and ammonium nitrate in a 20-liter glass carboy. This material was undergoing a volume reduction by boiling in a floor-type metal hood with Plexiglas sides and 3 sliding door on the front of ordinary glass. The alcohol vapor was vents directly into the hood (Fig1.)
Date: May 22, 1959
Creator: Lain, J. E. & Hungerford, T. W.
Partner: UNT Libraries Government Documents Department
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Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date: June 22, 1959
Creator: Blevins, E. L.
Partner: UNT Libraries Government Documents Department
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Internally Cooled Molten-Salt Reactors

Description: The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date: June 22, 1959
Creator: Lackey, M. E.
Partner: UNT Libraries Government Documents Department
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Notes on Heat Transfer in the ORR Core at Powers Greater Than 20 Mw

Description: One of the problems being considered in anticipation of raising the power of the ORR is the possibility of nucleate boiling due to excessive heat fluxes. This note is an attempt to analyze some of the worst conditions of a known core along with extrapolation to higher powers.
Date: September 22, 1959
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
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Programmers Manual: ORACLE Binary Internal Translator (ORBIT) - Algebraic Programming System for the ORACLE

Description: The present edition of the programmers manual for the ORACLE Binary Internal Translator has been completely revised and considerably expanded. At the same time, the Translator program itself has also undergone complete revision. The new version of ORBIT will accommodate programs written in accordance with the original instructions with minor exceptions.
Date: September 22, 1959
Creator: Grau, A. A.; Feliciano, M.; Caldwell, G. C.; Cooper, E. L.; Culkowski, A. & Harrison, J.
Partner: UNT Libraries Government Documents Department
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The Concentration of Peroxide in Uranyl Sulfate Solutions at Incipient Precipitation

Description: The concentrations of peroxide in uranyl sulfate solutions at incipient precipitation of uranium peroxide were determined over a temperature interval from 79 to 114'C. The results of the experimental observations have been used to calculate a self-consistent set of numerical parameters that are related to the equilibrium of hydrogen peroxide, uranyl ion and hydrogen ion.
Date: October 22, 1959
Creator: Gilpatrick, L. O.; Jolley, H. R.; Kelly, M. J.; Silverman, M. D. & Watson, G. M.
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.
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-
Partner: UNT Libraries Government Documents Department
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