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A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II

Description: From Abstract: "A detailed description is given of ARGUS, a FORTRAN II computer program for calculating transient temperatures in any concentric cylindrical configuration. Included are an explanation of the mathematical methods, a discussion of special features and restrictions, input and output descriptions, operating instructions, several sample problems, and the code listing."
Date: November 1963
Creator: Schoeberle, D. F.; Heestand, J.; Miller, L. B. & Miller, L. B.
Partner: UNT Libraries Government Documents Department
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Research on Thermoelectric Heat Pumps

Description: From Results: "Prior to stating results achieved, let us first discuss the measurements we were able to make, and how these measurements might--or might not--be indicative of the objective we strove to reach. Tables I and II, and related Figs. 11 and 12, show the best results obtained. Final Columns of Tables I and II are believed to show, at least to a degree, how good or how poor our best sputtered films turned out to be, compared with top-quality Peliter semiconductor materials."
Date: November 1963
Creator: Cox, E. F.
Partner: UNT Libraries Government Documents Department
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Demineralization by Transport Depletion

Description: Report concerning the demineralization of water via the transport depletion process, which is a variation of electrodialysis that uses just one ion-exchange membrane. The first portion of the report covers a year of studying the transport depletion method, while the second part includes details regarding the experiments, equipment, and complications in greater detail.
Date: November 1963
Creator: Lacey, Robert E.
Partner: UNT Libraries Government Documents Department
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Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors

Description: Report issued by the APDA over studies conducted on Doppler coefficient fast reactors. Calculations, methods, and results of the studies are presented. This report includes tables, and illustrations.
Date: November 1, 1963
Creator: Fischer, E. A.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Behavior of High Purity Uranium

Description: Report that "describes the behavior of small, high purity uranium specimens irradiated under controlled conditions" (p. 2).
Date: November 1963
Creator: Leggett, R. D.; Mastel, B. & Bierlein, T. K.
Partner: UNT Libraries Government Documents Department
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A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator

Description: Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical… more
Date: November 1, 1963
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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The Effect of Row Charge Spacing and Depth on Crater Dimensions

Description: From preface: The work described in this document is directed toward determining the optimum method of employing explosives to form a ditch, channel, or canal of certain desired dimensions.
Date: November 1963
Creator: Vortman, Luke J. & Schofield, L. N.
Partner: UNT Libraries Government Documents Department
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Oak Ridge Metals and Ceramics Division Annual Progress Report: 1963

Description: Report documenting research and developments made by the Metals and Ceramic Division of the Oak Ridge National Laboratory. Progress is reported on fundamental research in: crystal physics, reactions at metal surfaces, spectroscopy of ionic media, structure of metals, theory of alloying, physical properties, sintering, deformation of crystalline solids, x ray diffraction, metallurgy of superconducting materials, and electron microscope studies. Long-randge applied research studies were conducted… more
Date: November 11, 1963
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Partner: UNT Libraries Government Documents Department
open access

Shield Small Source Experiments. Summary Report

Description: A shielding experiment was performed that provided a proof test of the shield calculation methods used in the MCR shield desing and provides a partial confirmation of cross-section data. Measurements were made with a gamma spectrometer behind a configuration consisting of a layer of gamma shielding material followed by a neutron shield, with the configuration exposed to neutrons from a Po --Be source. The test configuration is illustrated. Secondary gamma rays produced in the assembly were meas… more
Date: November 1, 1963
Creator: Schamberger, R.; Celnik, J. & Ross, R.
Partner: UNT Libraries Government Documents Department
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Flow Controller Evaluation for Sodium Service

Description: Tests were conducted to evaluate the performance of a 10-in. flow controller in sodium at temperatures up to 1200 deg F. Torque tube reliability was determined by extensive mechanical cycling tests and further checking with a helium mass-spectrometer leak detector. Flow control performance and valve vibration characteristics were tested and evaluated and flow rate limits were established. The valve assembly was subjected to a thermal shock test program simulated to represent the most severe con… more
Date: November 30, 1963
Creator: Winborne, R. A.
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Substitution of Zircaloy for Stainless Steel in n.s. Savannah Fuel-Element Containers. Summary Report

Description: The possibility of reducing fuel-cycle costs for the N.S. SAVANNAH by replacing the stainless steel fuelelement containers in the permanent reactor core structure by similar containers of a zirconium alloy was investigated. These containers, although not integral parts of the fuel-bearing components, are located within the active core and divide the core into 32 separate channels into which the fuel elements are placed. Areas of investigation included reactor physics, fuel-cycle economics, mate… more
Date: November 1, 1963
Creator: Anderson, T. D.; Gross, E. E.; McCurdy, H. C.; Schaffer, L. D.; Shobe, L. R. & Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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CRITICAL EXPERIMENT WITH BORAX-V. Internal Superheater

Description: A critical experiment was performed with 12 BORAX-V superheater subassemblies in a central voidable region plus 1228 to 1525 UO/sub 2/ fuel pins (3 wt% enriched) in a peripheral region. Removing water (28% of superheater volume) at room temperature decreased reactivity by 2.2%. The midplane (two- dimensional) peak-to-average power distribution in the voided superheater was approximately 1.24, mostly attributable to flux depressions within insulated fuel boxes. Cadmium ratios are also reported. … more
Date: November 1963
Creator: Plumlee, K. E.; Baird, Q. L.; Stanford, G. S. & Amundson, P. I.
Partner: UNT Libraries Government Documents Department
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