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9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090

Description: The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format ha… more
Date: October 28, 1960
Creator: Stone, Stuart P.
Partner: UNT Libraries Government Documents Department
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ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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[Aerosol Generator Design] : Letter Report

Description: The following report provides information on an aerosol generator fit to produce fine particles by a vaporization-condensation technique. Included is a diagram of the essential components of the generator.
Date: October 19, 1960
Creator: Rosinski, John & Stockham, John D.
Partner: UNT Libraries Government Documents Department
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ALUMINA COATING OF UO$sup 2$ SHOT BY HYDROLYSIS OF ALUMINUM CHLORIDE VAPOR

Description: Uniform, dense coatings of alumina about 5 to 150 mu thick were applied to uranium dioxide particles 44 to 350 mu in diameter by hydrolysis of aluminum chloride vapor in a fluidized bed of the particles at 1830 deg F. The coated particles were resistant to nitric acid leaching, to oxidation in 1830 deg F air, and to thermal cycling from 6OO to 2500 deg F. After low neutron exposures, the coated particles showed excellent fission-gas retention at temperatures up to 2400 deg F in inert gas. Altho… more
Date: October 25, 1960
Creator: Browning, M. F.; Veigel, N. D.; Cook, T. E.; Diethorn, W. S. & Blocher, J. M., Jr.
Partner: UNT Libraries Government Documents Department
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Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Description: Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II an… more
Date: October 5, 1960
Creator: Paluszkiewicz, S.
Partner: UNT Libraries Government Documents Department
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Applied Mathematics Division Summary Report for July 1, 1958 Through June 30, 1959

Description: The objective of the Applied Mathematics Division is to provide mathematical assistance to other scientists in the Lab. This goal is achieved by (1) conducting research in numerical analysis and other branches of mathematics, (2) providing mathematical consultation, and (3) operating a computational service, using both digital and analog machines. Publications, papers, seminars, lectures, and courses are listed. A summary listing of computer programs developed or in progress is given. (For prec… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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Applied Mathematics Division Summary Report for July 1, 1959 Through June 30, 1960

Description: A summary of each computer program initiated during the report period together with code symbols indicating the extent to which information concerning the program is readily available are given. Programs previously reported are included if changes were made or additional information concerning them was placed in the program library. Abstracts of 704 newsletters and GEORGE bulletins are presented. (For preceding period see ANL-6089.) (W.D.M.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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AUEOUS CORROSION OF ALUMINUM AT 260 C

Description: Ten experimental alloys of aluminum containing up to 4% nickel corroded uniformly, without intergranular attack, when exposed for 3 months to flowing deionized water at 260 deg C. The average penetration rates were between 1.4 and 1.9 mils per month. (auth)
Date: October 1, 1960
Creator: Whatley, V.
Partner: UNT Libraries Government Documents Department
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Boiling Heat Transfer of Liquid Metals: a Literature Search

Description: This partially annotated bibliography contains references on boiling heat transfer of liquid metals. Emphasis is place on boiling heat transfer of liquid sodium, liquid potassium, and liquid rubidium. The period covered is 1950 to date. References are arranged alphabetically by title. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Nuclear Science Abstracts.
Date: October 3, 1960
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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BOTTOM-POUR RE-USABLE MELTING CRUCIBLES FOR PLUTONIUM CASTING

Description: 24p. Bottom-pour Ta and CaF/sub 2/-coated steel melt crucibles for Pu and Pu-rich alloys were developed. The controlled pour is effected by melting a Pu plug in the bottom spout of the crucible after the desired temperature and vacuum conditions are obtained. A description is given of the development of the crucibles which have replaced ceramic crucibles for casting work on the kilogram scale. (auth)
Date: October 1, 1960
Creator: Miley, F. & Anderson, J.W.
Partner: UNT Libraries Government Documents Department
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C pile mark 1 overbore fuel element design

Description: It is necessary to provide the option of using either aluminum or zirconium tubes in the C pile 20-tube overbore test. A bumper-type fuel element has been designed to fit a fixed ribbed aluminum tube size; zirconium tube dimensions were then determined which will provide the same flow and pressure drop when the fuel element is changed from bumper type or self-supported without changing other fuel dimensions.
Date: October 6, 1960
Creator: Cahoon, R. D. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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The Calculation of Transient Temperature Distributions in a Solid Cylindrical Pin, Cooled on the Surface

Description: The IBM-704 program RE-147 is used to calculate the time and space- dependent temperature distribution in a solid cylindrical fuel pin, cooled on the surface, with internal heat generation. The fuel pin may be bare or clad, and its boundary may be cooled by either flowing or staagnat coolant. The heat generatlon source may also be time and space dependent. Specifically, the program considers the fuel pin to be composed of two regions and then solves, by the usual finite difference methods, the … more
Date: October 1, 1960
Creator: Heestand, J.; Schoeberle, D. F. & Miller, L. B.
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, AND MARCH 1957

Description: Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution of uranium-- zirconium fuel alloys continued. In corrosion tests to find a suitable container material, Ni was found to be susceptible to a sulfur-type attack. Hastelloy B showed promise, and graphite offers excellent chemical resistance but poor mechanical strength. The dissolution rate of Zr in NaF-- ZrF as affected by impingement of the HF sparge was studied. Production of UF/sub 6/ by fluidi… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1960

Description: Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, July 1960

Description: A critical review of the literature revealed no experiments on uranyl ion transfer from an aqueous to a tributyl phosphate phase which positively measured the kinetics of the chemical reaction at the interphase. Drawing isorhythmic lines on a three component diagram gives a complex correlation for the compaction of three sizes of glass beads. Neither the use of thoria sols nor high feed solution concentrations of thorium nitrate gave any significant increase in mean particle diameters over thos… more
Date: October 27, 1960
Creator: Whatley, M E; Haas, P A; Horton, R W; Ryon, A D; Suddath, J C & Watson, C D
Partner: UNT Libraries Government Documents Department
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COMPARISON OF FEDAL MONITOR READINGS WITH RADIOCHEMICAL SAMPLE DATA. CORE I, SEED 1. Test Results T-641305

Description: Tests were conducted to compare the specific isotopic fission product activities with those of delayed neutron emitters which are monitored by the FEDAL System, and to obtain irformation on the source of activity observed in the PWR coolant. The monitors detected definite activity bursts of delayed neutrons during load increases, which indicated a rupture of the core blanket element. A radiochemical analysis of the coolant data did not show any unusual activity bursts, thus indicating a fuel el… more
Date: October 24, 1960
Partner: UNT Libraries Government Documents Department
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Compatibility of SNAP Fuel and Clad Materials

Description: Samples capsules containing buttons of materials of interest for SNAP fuel elements were held at temperatures up to 1600°F , in hydrogen, under a 20-tsi load for 200+ hours.
Date: October 15, 1960
Creator: Balkwill, J.K.
Partner: UNT Libraries Government Documents Department
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Correction to the Debye-Huckel Theory

Description: In a recent paper, Bowers and Salpeter described a method for calculating the correlation energy of a classical one-component electron gas. The same problem has been considered by Meeron, Friedman, and Abe, using methods involving the summation of cert infinite classes of diagrams. While the relation between these theories and that of Bowers and Saltpeter is not year clear, it is interesting to note that Abe obtained an equivalent expression by approximating an integral. We have calculated the … more
Date: October 7, 1960
Creator: Trulio, John G.
Partner: UNT Libraries Government Documents Department
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Critique - NPR fuel

Description: The current status of the NPR fuel fabrication and testing program has been reviewed; suggestions have been made concerning areas requiring more information. This report is divided into a series of sections, each of which is a complete entity so a specific problem area can be considered apart from the entire NPR Fuel process. The final section incorporating conclusions and recommendations reaffirms the factors of major importance as well as evaluating those areas which are interrelated. Process… more
Date: October 14, 1960
Creator: Bush, B. H.
Partner: UNT Libraries Government Documents Department
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Decontamination of EGCR Charge and Service Machines

Description: Methods for the noncorrosive removal of volatile fission products and UO2 dust from carbon steel and stainless steel have been developed. Procedures for applying these methods to the decontamination of the EGCR charge and service machines are described.
Date: October 13, 1960
Creator: Meservey, A. B.; Chilton, J. M. & Ferguson, D. E.
Partner: UNT Libraries Government Documents Department
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