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Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

Description: This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
Partner: UNT Libraries Government Documents Department
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The Crystal Structure of LiCuCl3-2H2O*

Description: This report undertakes research to study LiCuCl3-2H2O is from a structural standpoint, revealing the oxygen positions. The study uses the Levy-Bussing anisotropic temperature factor treatment and least squares program to determine a discrepancy factor for the visually determined intensities. The structure of the molecule is also found to have interesting magnetic properties which has inspired a new study at Brookhaven.
Date: 1960
Creator: Vossos, Peter H.; Fitzwater, D. R. & Rundle, R. E.
Partner: UNT Libraries Government Documents Department
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An Electrical Pass-Through for Clean, High Vacuum Use

Description: This report describes the method and research that led to the development of a "new type of mechanical seal for a high-voltage, vacuum pass-through...for use in a general utility 60º sector mass spectrometer." (From introductory paragraph)
Date: 1960
Creator: Jackson, Don M.; Wells, Garry & Soseman, Donald
Partner: UNT Libraries Government Documents Department
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Bismuth

Description: This report provides a broad and in depth discussion of bismuth, discussing the properties of bismuth--including physical, electrochemical, and chemical properties. It then discusses the processes by which bismuth is detected and how bismuth can be separated and isolated, with discussions of dissolution, precipitation, and extraction.
Date: 1960
Creator: Fritz, James S.
Partner: UNT Libraries Government Documents Department
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Photoproduction of Beryllium-7

Description: From abstract: "The nuclide Be7 has been produced by photoactivation of Be9, B and C12 using the bremsstrahlung beam of an electron synchrotron operated at 45 Mev. Integrated cross sections for the formation of Be7 have been estimated by comparison with the Ta181([gamma],n)Ta180m reaction. The reaction C12([gamma],2p3n)Be7 has also been observed in irradiations at 30, 35 and 40 Mev maximum energy. Its yield has been compared with that of the C12([gamma],n) reaction at 45 Mev. The reaction A127([gamma],2p3n)Na22 was observed at 45 Mev."
Date: 1960
Creator: Foster, M. S. & Voigt, A. F.
Partner: UNT Libraries Government Documents Department
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Seebeck Effect in Magnesium Silicide

Description: From abstract: "The Seebeck coefficient (thermoelectric power) has been measured from 7°K to 1000°K for both n-type and p-type single crystals of Mg2Si...The phonon contribution, Sp, was obtained from the measured Seebeck coefficient by subtracting off the electron diffusion term, Se, which was calculated with the aid of the measured Hall coefficient. The magnitude of Sp was observed to be proportional to T-3 and to show the dependence on sample size and on carrier concentration predicted by the theory of C. Herring..."
Date: November 1960
Creator: Heller, Marvin William & Danielson, G. C.
Partner: UNT Libraries Government Documents Department
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Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column

Description: From abstract: "Over-all mass transfer coefficients were determined by considering the operation of the pulse column to be a stage-wise process. The area for mass transfer was obtained by direct photographic measurements...The mass transfer coefficient was found to increase when the interfacial tension was reduced..."
Date: November 1960
Creator: Konopik, Alvin Eugene & Burkhart, Lawrence
Partner: UNT Libraries Government Documents Department
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Microwave Measurements of Hall Mobilities in Semiconductors

Description: From abstract: "The Hall mobilities of germanium single crystals were measured with a microwave frequence of 9000 Mc/sec over the temperature range 30°K to 300°K. A rectangular sample occupied the central part of the wall of a rectangular cavity, which was doubly generate in the TE101 mode and in the TE011 mode at a single resonance microwave frequency. The external magnetic field and microwave field associated with one of the two modes gave rise to the other mode of oscillation, owing to excitation by the microwave Hall field. The theoretical analysis was verified by measurements on an n-type sample having a room temperature resistivity of 0.40 ohm cm. The measured Hall mobility at microwave frequencies (with a size correction) was compared with the D.C. Hall mobility between 30°K to 300°K. The maximum discrepancy was 15%. The estimated experimental error in the microwave measurement was 16%. The magnetic field dependence of the microwave Hall mobility in a p-type sample, having a room temperature resistivity of a 0.77 ohm cm, was in qualitative agreement with the D.C. results obtained by Willardson et al."
Date: November 1960
Creator: Nishina, Yuichiro & Danielson, G. C.
Partner: UNT Libraries Government Documents Department
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Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Description: Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Partner: UNT Libraries Government Documents Department
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Scale "Up or Down" Analysis for Prototype Test

Description: Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date: May 1, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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SM-2 Fuel Element Welding Development : Task 5.0

Description: Abstract: Development of welding processes for stainless steel fuel elements, previously initiated by Alco Products, was continued in Task 5. Three objectives were accomplished; (1) development of a suitable reference welding process, (2) evaluation by out-of-pile tests of the structural integrity of reference welded fuel elements, and (3) preparation of specifications and fabrication procedures for the reference welding process.
Date: August 11, 1960
Creator: Harris, R. L.
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 and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.
Date: October 5, 1960
Creator: Paluszkiewicz, S.
Partner: UNT Libraries Government Documents Department
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SM-1 Research and Development Program: Long-lived Induced Activity Buildup During SM-1 Core I Lifetime. Task XVIII, Phase I

Description: Abstract: The results of activity buildup studies in the SM-1 performed during Core I lifetime (June 3, 1957 to April 28, 1960) are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Radiation levels after reactor shutdown are presented, as well as mathematical equations used to account for the observed activity levels. The data have shown that Co60 is the major contributor to radiation levels in the SM-1. Co60 activity arises from the cobalt in Haynes 25 alloy flux suppressors, and the cobalt impurity in stainless steel. After 35 months operation at an average power level of 55%, deposited Co60 activity accounted for approximately 83% of the total radiation level (mr/hr) contributed by the long-lived gamma emitting nuclides. The contribution of the primary coolant activity to the total radiation level is insignificant when compared to the contribution of the activity deposited on the walls of the system. The radiation level on the super-heater side of the steam generator was about 1400 mr/hr after 35 months of reactor operation. The percentages of Co60 activity in the coolant and in the deposits were not the same. This indicates either that nuclides are depositing irreversibly on the surface of the system, or that all nuclides are not exchanging at the same rate. The ratio of Co58/Co60 in the deposits shows that a major fraction of the nuclides are irreversibly deposited. Mathematical equations derived during the course of work were used to predict the observed activity buildup on SM-1 primary system surfaces. Certain constants in the the equations were obtained from the experimental data. Calculated values of activity levels based on the equations were in good agreement with the activity levels found on the primary system. The equations may be …
Date: November 30, 1960
Creator: Bergmann, C. A.; Bergen, C.; Cox, J. F.; Chupak, J. & Grant, L. G.
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design

Description: This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. 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 fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a boiler section, (2) a steam drum, and (3) a superheater section. These three sections are combined into a single unit construction with a large sphere as the steam drum connecting the boiler and superheater section. This design makes a relatively long unit but has the advantage of reducing costs since the steam drum acts a a closure for one end of the boiler and superheater and eliminates the need for external connecting piping.
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis

Description: Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions for using creep and stress rupture properties.
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications

Description: Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance

Description: This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level Detector, and (d) Sodium Purity Control Recommendations.
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Analog and Digital Readout on an IBM Output Writer

Description: Abstract: A control system to provide digital printing and to plot an analog trace on an electric operated IBM model 11C Output Writer is described. The Digital mode of operation translates multidigit numbers through a set of commands to print each digit serially, then presents them to the output writer in a time sequence. The Analog mode of operation converts a d.c. input voltage to a digital number and by tab and space bar commands translates the carriage horizontally a distance proportional to this number.
Date: September 7, 1960
Creator: Graveson, R. T. (Robert T.)
Partner: UNT Libraries Government Documents Department
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The Effects of Fuel Rod Fission Product Leakage on the Consolidated Edison Thorium Reactor Plant

Description: Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem
Date: June 1960
Creator: Montgomery, D. W.; Howard, J. O. & Dodd, R. H.
Partner: UNT Libraries Government Documents Department
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