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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.
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
Partner: UNT Libraries Government Documents Department
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Yankee Atomic Electric Company Research and Development Program: Quarterly Progress Report: October 1, 1958 to December 31, 1958

Description: Quarterly report describing the technical research and development work accomplished by the Yankee Atomic Electric Company Research and Development Program, and documenting progress made on the group's various projects and goals.
Date: February 16, 1959
Creator: Garbe, R. W. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department
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Report of the Fluid Fuel Reactors Task Force

Description: From preface: This report was prepared by a task force that met continuously in January and February of 1959 for the purposes of making a relative comparison of the fluid fuel reactor concepts for technical feasibility.
Date: February 1959
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
Partner: UNT Libraries Government Documents Department
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A Synopsis of Studies Related to Tritium Monitoring and Personnel Protective Techniques

Description: Technical report issued by E. I. du Pont de Nemours & Co. From Abstract: "Information obtained from investigations pertinent to tritium monitoring and protective measures at the Savannah River Plant are given. These findings were used to establish realistic protective techniques and consequently, to insure the safety of workers exposed to this hazard. Topics included are: contamination, permeation of plastics and rubber, instrumentation, and biological and physical aspects."
Date: February 1959
Creator: Butler, Harry L. & Van Wyck, Robert W.
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.
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.
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)
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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Uranium Reconnaissance and Drilling in the Sanostee Area, San Juan County, New Mexico and Apache County, Arizona

Description: Report documenting work to map in detail the Roy Mesa and Enos Johnson claim areas so that ore guides could be determined and the areas could be evaluated for drilling and to complete a general reconnasaince of the favorable Mesozoic.
Date: February 1959
Creator: Blagbrough, John W.; Thieme, D. A.; Archer, B. J., Jr. & Lott, R. W.
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.
Partner: UNT Libraries Government Documents Department
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Results of Experiments Made With U.S.B.M. Electrocerium

Description: Data obtained in test of Bureau of Mines electrocerium are presented. The cerium was subjected to spectrochemical analysis, x-ray diffraction analysis, thermal analysis, metallographic tests, and high-pressure experiments.
Date: February 26, 1959
Creator: Miner, William N.
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.
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.
Partner: UNT Libraries Government Documents Department
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Rod Drop Transient. Test Results DL-S-247 (T-641323). Section I

Description: The purpose of the test was to obtain data on plant performance after a single rod has been dropped with the plant at 13 mw gross generator output. The operation of the plant after a single control rod (No. 23) had been dropped was within allowable limits. The high speed recorder charts could not be evaluated accurately due to the fast chart speed and also because they were calibrated to cover a much wider range than was necessary. The necessary data was obtained from the normal plant records i… more
Date: February 16, 1959
Creator: Price, F. C.
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.
Partner: UNT Libraries Government Documents Department
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