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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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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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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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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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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Tenth Letter Report, October 1 to December 1, 1959

Description: Introduction: "This is the tenth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from October 1 to December 1, 1959."
Date: December 18, 1959
Creator: Stockham, John D. & Rosinski, John
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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Fission Gas Generation and Consequent High Temperature Irradiation Effects on Natural Uranium, Including Creep Properties : a Literature Search

Description: Sixty-two references, some annotated, were taken from foreign literature to determine the status of work done in this area of metallurgy during 1958 and 1959. The references are grouped into two categories: references pertinent to the subject and general metallurgical references on metallic fuels.
Date: December 15, 1959
Creator: Scott, Myra
Partner: UNT Libraries Government Documents Department
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Hazards Analysis of the Organic Moderated Reactor Experiment

Description: Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
Date: December 15, 1959
Creator: Williams, R. O., Jr.; Allen, W. O.; Ash, E. B.; Scott, W. W.; Shimazaki, T. T.; Sletten, H. L. et al.
Partner: UNT Libraries Government Documents Department
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Ionium (Thorium-230) for Radioisotope Preparation (Status Report)

Description: For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations… more
Date: December 15, 1959
Creator: Coppinger, E. A. & Rohrmann, C. A.
Partner: UNT Libraries Government Documents Department
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Nuclear Powered Tanker Design and Economic Analysis - Direct Cycle Boiling Water Reactor

Description: A design and economic analysis is presented for a 44,000 DWT tanker utilizing a 27,300 shp direct cycle boiling water reactor propulsion system. Included are design descriptions and drawings, estimates of operating and capitol costs for the reference ship, estimates of long range potential, descriptions of required research and development programs, a preliminary safeguards analysis, an analysis of ship's motion on boiling water reactor performance, a summary reactor physics analysis, and a dis… more
Date: December 15, 1959
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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