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The Chemistry and Nuclear Chemistry of the Heavy Elements : Progress Report No. 4

Description: This progress report covers the work on the project approximately between the dates June 1, 1058 and May 30, 1959, and is being submitted ahead of the contractual expiration date to support the request for renewal action. During the previous year work has continued to progress in the nuclear and inorganic sections of our heavy element group. The low-level counting equipment will make it possible to extend our fission studies to much lower energies. The U235 and U236 alpha induced fission is ess… more
Date: February 1959
Creator: Cobble, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid

Description: Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."
Date: February 1959
Creator: Tober, Frank W., 1919-1995 & Russell, Edwin R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section I. Third Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod combinations are charted in the report.
Date: February 12, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume 1, Contamination and Decontamination in Nuclear Power Reactors

Description: Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caus… more
Date: February 13, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination

Description: Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generat… more
Date: February 15, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume III, Recommended Procedure for Decontamination of a Stainless Steel Steam Generator

Description: Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.
Date: February 13, 1959
Creator: Pancer, Guyon P. & Zegger, John L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of the Chemical Characteristics of the 1C Boiler. Test Results DL-S-209. Section III

Description: The purpose of the test was to determine the chemical operating characteristics of the 1C Boiler. The results of the tests performed on the 1C Boiler prior to the installation of new riser indicated that definite chemical hideout existed during full load operation of the boiler. Measurement of local concentrations further indicated that a stabilized steam picket existed in the upper region of the heat exchanger adjacent to the inlet tube sheet during high steaming rates. Since these test were p… more
Date: February 9, 1959
Creator: Kline, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Heat Transfer in an Annulus with Asymmetric Heating

Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. V. & Reynolds, William C., 1933-2004
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Illustrations: Figures 1-10]

Description: Maps and charts illustrating aspects of a photogeologic reconnaissance study of the spatial relationship of uranium deposits to structure and stratigraphy in Duval County, Texas.
Date: February 1959
Creator: Barnes, John C.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department
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Interim Report on a Study of the Use fo Furnace Calorimetry for the Rapid Determination of Specific Heat of Solids at High Temperatures

Description: This project has accomplished the following items in the first year of work. (1) Design and construction of a vacuum furnace system which can attain temperatures up to 3000 F in a cylindrical column approximately 4 inches in diameter and six inches high, with ordinary voltages and current flow. (2) Investigation of the usefulness of the furnace system for comparative calorimetry at temperatures up to 1500 F. (3) Analysis of the comparative calorimetry method of measuring specific heat to determ… more
Date: February 1959
Creator: Boggs, J. H. & Wiebelt, John A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low-Energy [pi] Mesons in the Cosmic Radiation

Description: The intensity of 𝜋 mesons in the atmosphere is investigated in the energy region 𝐸kin≲50 Mev at sea level and at mountain altitudes. Positive 𝜋 mesons coming to rest in an absorber-scintillator are identified by the characteristic 𝜋−𝜇 decay. They are detected electronically and recorded photographically. The value 1.45±0.09 is adopted for the negative-to-positive ratio at small energies. The omnidirectional intensities 𝐽𝜋+ of slow positive 𝜋 mesons at sea level (91m), Echo Lake, Colorado (326… more
Date: February 2, 1959
Creator: Fotino, Mircea
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions

Description: Technical report. From Abstract: "Precipitation of manganese dioxide in solutions of uranium-aluminum alloy effected maximum removal of fission products when the alloy solutions were acid deficient. Minimum adsorption of uranium and minimum volume of centrifuged MnO2 were obtained by precipitation in acidic solutions with vigorous agitation."
Date: February 1959
Creator: Henry, Hugh E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

Description: Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
Date: February 1959
Creator: Argonne National Laboratory. Particle Accelerator Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Particle Extraction III

Description: A device to extend the operation of a beam extraction system is described for low energies where the radiation loss per turn is ineffective. The device consists of a noisy radiofrequency field which excites the radial betatron oscillation
Date: February 16, 1959
Creator: Robinson, Kenneth W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Processing of the Commission Blend of Colorado Front Range Uranium Ores

Description: Acid and alkaline processing of Commission Blend Colorado Front Range uranium ores is described. The composition of the blend is listed according to source and chemical composition. The processes investigated in laboratory and pilot plant work included concurrent and countercurrent acid leaching, alkaline leaching, and recycle of alkaline leach solution. In addition pre-roasting followed by acid and alkaline leaching, flotation of carbon and sulfides followed by acid leaching the concentrate, a… more
Date: February 1959
Creator: Nichols, I. L. (Ivan L.); Ross, J. R.; Tame, K. E. & Rosenbaum, J. B. (Joe B.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Processing of the Cotter Blend of Colorado Front Range Uranium Ores

Description: The results of laboratory and pilot plant alkaline leaching of the calcareous Cotter Blend are described. The Cotter Blend composition is given in relation to the source and chemical composition. It was demonstrated that specification-grade yellow cake with high recovery of uranium could be produced from Cotter Blend by a pressure alkaline leaching process. A pressure leach under oxygen pressure followed by caustic precipitation recovered 93.1% of the Uranium. (J.R.D.);
Date: February 1959
Creator: Nichols, I. L. (Ivan L.); Tame, K. E. & Rosenbaum, J. B. (Joe B.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactions of Metals with Oxygen and Steam. Final Report for June 15, 1958 - February 15, 1959

Description: Titanium, zirconium, and Zircaloy can spontaneously ignite under relatively mild conditions. The effect of temperature, oxygen concentration and pressure, and the nature of the diluent on the spontaneous ignition of titanium, zirconium, and Zircaloy were investigated.
Date: February 15, 1959
Creator: Littman, Fred E. & Church, Frank M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Automatic Control and Load Swing Tests. Test Results DL-S-144 (T-554924). Section I

Description: The purpose of this test was to determine the controlling ability of the Reactor Power and Temperature Control System and to determine the operational characteristics of the station during load swings. The Reactor Power and Temperature Control System satisfactorily controlled rod movements to maintain all primary plant parameters within their individual limits during steady state operation, ramp functions load changes and a peak xenon burnout transient. The operational characteristics of the st… more
Date: February 10, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reconnaissance for Uranium in the Tocopilla area, Province of Antofagasta, Chile

Description: Abstract: In September-October 1958 a six-day reconnaissance in the Tocopilla area, Antofagasta Province, Chile, was made by members of the U.S. Atomic Energy Commission and the Instituto de Investigaciones Geológicas de Chile for the purpose of evaluating reported uranium occurrences.
Date: February 1959
Creator: Bowes, William A.; Knowles, Paul H.; C., Mario Serrano & S., Rudolfo Grüenwald
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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