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Absorption of Organic Acids on Thoria

Description: The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date: December 31, 1959
Creator: Bradford, Harold R. & Wadsworth, Milton E.
Partner: UNT Libraries Government Documents Department
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Annual Report of Research Progress

Description: This technical report constitutes a brief review of the work undertaken, entirely or in part, under the Contract AT(30-1)-1772 with eh United States Atomic Energy Commission. The work published during 1959 is listed at the end of this report and copies of the reprints or reports are attached where available. These investigations have been concerned with the examination of defect production and behavior as it may be observed by high frequency ultrasonic attenuation and velocity (modulus) changes… more
Date: December 31, 1959
Creator: Truell, Rohn, 1913-1968
Partner: UNT Libraries Government Documents Department
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Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959

Description: Attempts to secure a high degree of synchronization of cell division of the Krebs mouse ascites carcinoma, by combined use of aminopterin and citrovorum factor, and by use of colchicine and N-acetyl colchinol, were unsuccessful. In the course of the work, a new method for securing smears of ascites tumor cells was out, which we believe will be found useful
Date: December 31, 1959
Creator: Beck, Lyle Vibert, 1906-
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, August 1959. Chemical Technology Division

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed, two Druhm runs were terminated due to malfunction, calculations of particle temperature were performed, materials handling flowsheets were completed, and a literature survey is being conducted.
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. (Marvin E.), 1926-
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.
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.
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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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.)
Partner: UNT Libraries Government Documents Department
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Self-Shielding Cross Sections : a Bibliography

Description: This bibliography contains 37 references on self-shielding cross sections. The bibliography is limited to the period from 1951 through November 1959 with the references arranged alphabetically by title. The sources used in compiling this bibliography were: Abstracts of Classified Reports Nuclear Science Abstracts
Date: December 29, 1959
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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Development and Testing of an Improved Agitator for the Redox and Purex Separations Plants

Description: Relatively frequent agitator failures in HAPO Separations Plants have interfered with process continuity, contributed to process difficulties, and resulted in considerable maintenance expense. Predominantly the failures have been because of gear-reduction drive unit break-down or because of metallic fatigue and degeneration of the shaft-paddle assemblies. A simplified, slow-speed, direct drive agitator, previously described in HW-52755, proved to be quite durable and satisfactory during extende… more
Date: December 24, 1959
Creator: Dunn, J. & Sloat, R. J.
Partner: UNT Libraries Government Documents Department
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Organic Coolant Reclamation Annual Report : December 15, 1958 through December 14, 1959

Description: Potential methods have been examined for the reclamation of high boiler arising from the degradation of polyphenol materials in use as reactor coolants and moderators. To define the chemistry of potential reclamation processes, model polyphenol compounds were used. These include biphenyl, o, m and p-terphenyl, and p-quaterphenyl. Emphasis has been on hydrocracking, redistribution (reaction with benzene), and partial reduction. Preliminary study has been made of the application these techniques … more
Date: December 23, 1959
Creator: Wineman, Robert J.; Adams, J. S.; Gudzinowicz, Benjamin J. & Scola, D. A.
Partner: UNT Libraries Government Documents Department
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Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

Description: It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stabi… more
Date: December 23, 1959
Creator: Allen, C. W.
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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Design Criteria for PRP- Critical Facility Project CAH-842

Description: The PRP Critical Facility is an experimental reactor for use in determination of basic nuclear constants of heterogenous reactors recycling plutonium, and exponential and criticality studies at power levels up to 100 watts and neutron fluxes of about 109 nv. Provision is made for changing reactor lattices using irradiated and unirradiated fuel elements with either a light or heavy water moderator.
Date: December 18, 1959
Creator: Nelson, H. K. & O'Neill, G. L.
Partner: UNT Libraries Government Documents Department
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Report of the Forty-Fourth National Conference on Weights and Measures, 1959

Description: Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Date: December 18, 1959
Creator: United States. National Bureau of Standards.
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.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Annual Progress Report, September 1, 1959

Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: December 16, 1959
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section I. EFPH-5465.2. Second Performance. Core I, Seed 1. Test Results DL-S-231, T-612394

Description: The purpose of the test was to determine the radiation levels in a Reactor Plant Boiler Compartment with the respective loop shut down and the remainder of the plant operating at power. The highest radiation levels recorded in the IC Boiler Compartment were located in the vicinity of the reactor coolant loop pipe penetrations of the Compartment. Except for the above mentioned areas, personnel could continuously occupy the IC Boiler Compartment without exceeding the maximum dose rate of 300 mr p… more
Date: December 16, 1959
Creator: McTish, James M.
Partner: UNT Libraries Government Documents Department
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Thermodynamic Properties of Selected Minerals and Oxides at High Temperatures

Description: A report about thermodynamic properties of several minerals which have been constructed in a form convenient for calculation of chemical equilibria of minerals and of problems related to the heat content of rocks.
Date: December 16, 1959
Creator: Robie, Richard A.
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-
Partner: UNT Libraries Government Documents Department
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