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Recording Equipment for Internal Friction Measurements

Description: An apparatus was developed for recording internal friction data in such a manner as to circumvent many of the laborious and time-consuming observations and calculations usually associated with these measurements. An optical lever is used and the passage of the beam across the scale is detected by photoconductive cells. The cells are strategically located so that, when their signals are fed through a multichannel switching circuit to the pens of an operation recorder, a plot of the logarithm of … more
Date: October 31, 1961
Creator: Stephenson, R. L. & McCoy, H. E. Jr.
Partner: UNT Libraries Government Documents Department
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Proceedings of the University of New Mexico Conference on Organic Scintillation Detectors, August 15-17, 1960

Description: Twenty-three papers are included which were presented at the Conference on Organic Scintillation Detectors. The topics treated range from measurements of organic phosphor properties to liquid and plastic scintillation detectors. Separate abstracts were prepared for each of the papers. (D.L.C.)
Date: October 31, 1961
Creator: Daub, G. H.; Hayes, F. N. & Sullivan, E.
Partner: UNT Libraries Government Documents Department
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A PROGRAM OF RESEARCH ON MECHANICAL METALLURGY AS RELATED TO FUEL-ELEMENT FABRICATION. Quarterly Progress Report for the Period Ending June 30, 1961

Description: Results of crawing experiments using 3/8-in. bars to provide rod and tube test specimens are reported. In mechanical metallurgy investigations on the relation of formability to imperfection structure the peierls potentials for dislocation of Nb, Mo, Ta, and W were measured. Design and construction of a microextensometer reported. The investigations of the effects of grain size on the stored energy cold work were extended to a new lot OFHC Cu. In studies of formability relations with imperfectio… more
Date: August 31, 1961
Creator: Trozera, T Z; Koyama, K; White, J L & Chambers, R H
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for Period April 1 through June 30, 1961

Description: BS>Activities are discussed for work done in the preparation of PuO/sub 2/ using the continuous oxalate process, and continuous coprecipitation studies using a uranium-20 wt% plutonium nitrate feed solution. Characterization studies of the PuO/sub 2/ powders indicated that variations in the processing variables can affect the final product. Measurements with the B. E. T. and Innes apparatus confirmed that the specific surface area of the initial batch of the PuO/sub 2/ powder had increased appr… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL APPARATUS AND TECHNIQUES FOR HIGH TEMPERATURE COMPATIBILITY STUDIES

Description: The development of apparatus and laboratory techniques for the study of materials compatibility with 1500 to 2200 deg F potassium was attempted. Techniques for corrosion tab preparation, dry box capsule filling and sampling, and vacuum filling and sampling are described. Apparatus for rotating capsule testing to 2000 F, rotating capsule testing to 2400 deg F, and anisothermal see-saw'' capsule testing is also described. (auth)
Date: May 31, 1961
Creator: Smith, W.T.
Partner: UNT Libraries Government Documents Department
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Thermionic Isotopic Power Systems SNAP Programs. Quarterly Progress Report No. 7, Covering Period April 1 Through June 30, 1961

Description: An extensive parametric study of cesium-filled converters was completed during the quarter. Cesium-filled test units Nos. 2 and 3 were designed and constructed, and Unit 1 is 85% complete. The prototype vacuum thermionic converter, Unit 2B, was subjected to dynamic testing following its failure due to emitter poisoning. The analysis and design of the curium fuel capsule were completed. (auth)
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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NUCLEAR SUPERHEAT PROJECT SEVENTH QUARTERLY PROGRESS REPORT, JANUARY-MARCH 1961

Description: Progress and results from the conceptual design, economic evaluations, and research and development work performed as part of the Nuclear Superheat Project are reported. Developments in conceptual design and program evaluation, fuel technology, materials development, experimental physics, coolant chemistry, heat transfer, mechanical development, SADE, and mixed spectrum superheat design are discussed. (M.C.G.)
Date: October 31, 1961
Creator: Pennington, R.T.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961

Description: The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulat… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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High-Temperatuer Creep Evaluation in Carbon Dioxide Atmosphere : Summary Report, October 1, 1959 to March 31, 1961

Description: This report follows an investigation made to determine creep-rupture data for three sheet materials. Fourteen of sixteen tests were made in an atmosphere of carbon dioxide within hermetically sealed capsules, analyzing the reaction of the three sheet metals: 347 stainless steel, iron-aluminum-chromium alloy designated 261C, and a zirconium-base alloy, AE1H. Minimum creep rate, per cent elongation, and rupture life were determined and reported.
Date: March 31, 1961
Creator: Domagala, R. F.
Partner: UNT Libraries Government Documents Department
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Radioactive contamination in liquid wastes discharged to ground at separations facilities through December 1961

Description: This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1961. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of July through December 1961. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1961.
Date: December 31, 1961
Creator: Backman, G. E.
Partner: UNT Libraries Government Documents Department
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Defect-tests of power generating co-extruded fuel rods

Description: The effect of the many parameters which may influence the failure behavior of coextruded fuel material are being evaluated by Reactor & Fuels Research & Development Operation. This knowledge will be helpful in the design, fabrication, and operation of fuel elements so that the hazards and time involved at failure may be minimized. Many of the various tests performed on unirradiated coextruded fuel material have been in isothermal systems. The tests reported here were performed on power generati… more
Date: May 31, 1961
Creator: Goffard, J. W. & Hayden, K. D.
Partner: UNT Libraries Government Documents Department
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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Description: Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
Partner: UNT Libraries Government Documents Department
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PREPARATION OF HIGH-DENSITY, SPHERICAL THORIUM OXIDE PARTICLES WITH UP TO 10 ATOM PERCENT URANIUM

Description: A discussion is given of a fabrication process for preparing spherical particles of thorium oxides containing 10 wt.% uranium homogenously distributed throughout the thoria matrix from a sol prepared from Th(NO/sub 3/)/sub 4/ reaction with NH/sub 4/OH, in which uranyl nitrate is dissolved. The particles formed are 5 to 50 microns in diameter. The process is felt to be adaptable to large-scale production. (B.O.G.)
Date: October 31, 1961
Creator: Crouthamel, C.E.; Knapp, W.G.; Skladzien, S.B. & Loeding, J.W.
Partner: UNT Libraries Government Documents Department
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Mound Laboratory Progress Report for January 1961

Description: Work was begun to determine the physical properties of mica-filled diallyl phthalate. Both the impact and tensile strength values compared favorably wlth asbestos-filled DAP formulatlons. The tensile values compared with the upper limit tensile strength values for asbestos-filled formulations. Adiprene-ferric acetyl acetonate-polyol systems were developed as adhesives and their properties studied. Sources of kilogram quantities of Th/sup 2//sup 3//sup 0/ were investigated. The samples were anal… more
Date: January 31, 1961
Creator: Eichelberger, J.F.
Partner: UNT Libraries Government Documents Department
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Extrusion of I and E `O` size tubing to evaluate reduction in extruded O.D. and the use of pressed salt follower blocks: Experiment Number U-21

Description: The object of this experiment was to extrude normal uranium hollow billets to I and E `O` size tubing with reduced extruded O.D. and also to evaluate the use of pressed salt follower blocks. Pressed salt (NaCl) follower blocks under various conditions of pre-heat temperature were compared with the standard graphite at 800 F. Even though some yield reduction results, it was concluded that pressed salt follower blocks at 300 F represent a substantial cost reduction due to the extreme price differ… more
Date: January 31, 1961
Creator: Puterbaugh, J.F.
Partner: UNT Libraries Government Documents Department
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Elastic Scattering of 31-Mev He$sup 3$ Ions From Several Elements

Description: The absolute differential cross sections for elastic scattering of 31- Mev He/sup 3/ ions on Be, Al, Cu, Sn/sup (nat)/, Sn/sup 120/ and Bi were measured in the angular range of approximately 10 to 120 deg in the center-of-mass system. Thin selfsupporting foil targets were chosen to span the parameter A/sup 1/3/, where A is the target mass number. The first excited states of the isotopes of these elements had sufficient energy separation from the ground state to enable elastic scattering to be r… more
Date: December 31, 1961
Creator: Igo, G.; Vidal, J. G. & Markowitz, S. S.
Partner: UNT Libraries Government Documents Department
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Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Final Report, Phase I

Description: Activities in a program to develop techniques of plasma spraying clad plate-type UO/sub 2/ fuel elements are reported. The investigation was also directed toward determining the limitations of the process as applied to fuel element fabrication. UO/sub 2/ powder coatings having densities of 90% theoretical were produced. At conditions required for spraying plates, densities of 86% appear to be practical. The rate and efficiency of UO/sub 2/ coating deposition were also determined for various spr… more
Date: October 31, 1961
Creator: Weare, N. E.
Partner: UNT Libraries Government Documents Department
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The Cesium-137 Power Program. Quarterly Report No. 3

Description: Progress made in the development of the Cs/sup 137/ fueled thermoelectric generator for marine power applications is reported. Information is given on thermoelectric generator design, shielding, power conversion system, hazards evaluation, fuel element forming and cladding, fabrication, and heat transfer. Cs/sup 137/ energy calculations are presented along with shielding calculations. The development and fabrication of cesium polyglass for fuel application are included. (N.W.R.)
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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Health Physics Division Annual Progress Report, for Period Ending July 31, 1961

Description: Progress is reported in 26 papers on radioactive waste disposal, ecologicah research, radiation physics and dosimetry, internal dosimetry, and health physics technology. Twenty-five separate abstracts were prepared. One paper was previously abstracted for NSA. (M.C.G.)
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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Parameters in the Conversion of Plutonium Nitrate to Plutonium Trichloride by a Direct Calcination--Fluid Bed Chlorination Process

Description: Results of studies of the known parameters for direct calcination of plutonium nitrate in an agitated bed and conversion of PuO/sub 2/ to PuCl/sub 3/ by fluid bed processes are presented. A description of the processes and the demonstration equipment is included. The study of variables is discussed along with the parameters and plans for demonstration runs. (J.R.D.)
Date: May 31, 1961
Creator: Rasmussen, M. J.; Stiffler, G. L. & Hopkins, H. H., Jr.
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Phase II Summary Report, November 1, 1959 to October 31, 1960

Description: Coatings on the fuel element surface and coatings on individual fuel particles are being investigated for retaining fission products in fuel for the Pebble Bed Reacter. Ten fuel element specimens with surface coatings were subjected to varying amounts of high level irradiation. Cracks or pinholes were found in 6 of the coatings. Evidence indicated that the graphite matrix contributed to most of the failures. Release factors of the order of 10/sup -9/ for the Si--SiC coating under high-level irr… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATION ON BURNOUT HEAT FLUX WITH BOILING WATER. Final Summary Report, October 3, 1960-July 31, 1961

Description: Experimental results were obtained on the effect of an ultrasonic field on the burnout heat flux for water flowing at atmospheric pressure, through an annular flow channel formed by a 1/4-in.-diameter electrically heated tube and a concentric glass tube of 3/4-in. ID. The active length of the central heating element was 5 1/2 in. The ultrasonic transducer, which was operated at 25,000 cps and a maximum electrical input of 300 watts, was located at the inlet end of the flow channel. The ultrason… more
Date: July 31, 1961
Creator: Romie, F.E. & Aronson, C.A.
Partner: UNT Libraries Government Documents Department
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