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Study of Instrumentation and Techniques for Monitoring Vehicle and Equipment Environments at High Altitude: Effects of High-Altitude Environments on Vehicles and Equipment

Description: Report describing a study on the effects of high-altitude environments on vehicles and equipment presenting results indicating which environments are determined to be deleterious to the vehicle. Section I gives a summary of the environments encountered by the vehicles. Section II consists of an analysis of the effects of the environments on typical vehicle materials. Section III consists of an analysis of the environmental effects on typical vehicle subsystems. Section IV consists of a summary … more
Date: June 1960
Creator: Wacholder, B. V. & Fayer, E.
Partner: UNT Libraries Government Documents Department
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Study of Instrumentation and Techniques for Monitoring Vehicle and Equipment Environments at High Altitude: Vehicles and Environments

Description: Report describing a study of typical vehicles and the operating environments in the region of space between the earth and the moon. Vehicle characteristics, functions, and operating mediums for each are discussed, along with characteristics of the environments encountered by these vehicles. The discussion includes description, magnitude, and location of physical environments and electromagnetic environments. A glossary of terms and bibliography is included.
Date: June 1960
Creator: Wacholder, B. V. & Fayer, E.
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Selected Alloys at Elevated Temperatures, Part II: Design Criteria of Silicon Carbide

Description: Report describing a research study to determine in broad parameters the areas where a brittle, non-metallic body such as silicon carbide might be used in aircraft construction and establishing methods for obtaining these properties. A theoretical and literature review, design parameters, discussion of the testing phase, and test specimen geometry explanation are included.
Date: March 1960
Creator: Pearl, Harry A.; Nowak, John M. & Deban, Harry G.
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Selected Alloys at Elevated Temperatures [Pt. 1]

Description: Report describing a research study to provide material property data of the type and quality necessary for efficient design of hot aircraft and missile structural components. Six materials in plate and bar form were subjected to tension, compression, bearing, and shear stresses at various temperatures. Preliminary considerations of the study, testing apparatus, calibration and accuracy of the equipment, testing procedures and results are discussed.
Date: March 1960
Creator: Pearl, Harry A.; Kappelt, George F. & King, Edmund J.
Partner: UNT Libraries Government Documents Department
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Mechanical Property Survey of Refractory Nonmetallic Crystalline Materials and Intermetallic Compounds

Description: Report surveying literature on the mechanical properties of nonmetallic polycrystalline compounds and intermetallic compounds with melting points above 1500°C. Data collected on physical, mechanical, and thermal properties of the compounds is presented in summary tables and figures, with interpreted data separated into six appendices, each discussing a separate mechanical behavior of the materials.
Date: January 1960
Creator: Smiley, William D.; Sobon, Leon E.; Hruz, Frank M.; Farley, Eldon P.; Chilton, J. Emery; Poncelet, Eugene F. et al.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report February 1960 - Chemical Technology Division

Description: Summaries of progress are presented for Fuel cycle development, GCR coolant clean up studies, HR Thorium blanket studies, Ion exchange, Power reactor fuel processing, Solvent extraction studies, Volatility, and Waste processing
Date: May 18, 1960
Creator: Whatley, M. E. (Marvin E.), 1926-; 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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A Study of the Fuel Value of Plutonium

Description: The fuel value of mixtures of plutonium isotopes has been calculated for five thermal reactors (Yankee, Dresden, Hallam, GCR-II, Carolinas-Virginia)
Date: February 11, 1960
Creator: Jaye, S.; Bennett, L. L. & Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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Assay Methods Used In The ORNL Radioisotope Program

Description: A brief description is given of methods used in the measurement of radioactive content of radioisotopes distributed by the Oak Ridge National Laboratory. A tabulation of the techniques employed for seventy eight nuclear species is presented.
Date: February 1, 1960
Creator: Reynolds, S. A.
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Progress Report for October Through December, 1959

Description: The status of the Eurochemic (European Company for the Chemical Processing of Irradiated Fuels) Organization and the preliminary plant design are summarized. This report covers the progress during the period October through December 1959, gives the status of the program as of January 1, 1960, and outlines the anticipated assistance from the United States for the next 6 months.
Date: March 31, 1960
Creator: Nicholson, E. L. & Shank, E. M.
Partner: UNT Libraries Government Documents Department
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Observed Heat Transfer In HRT Fuel And Blanket Heat Exchangers

Description: Data obtained during power operation of the HRT indicates that during the circulation of fuel solution at high temperatures for more than 260 days there was a small increase in heat transfer resistance in the heat exchangers. The change in heat transfer correlates with the increase of the amount of corrosion product solids in the reactor fuel system.
Date: February 8, 1960
Creator: Haubenreich, P. N.; Piper, H. B.; Buxton, S. R. & Engel, J. R.
Partner: UNT Libraries Government Documents Department
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Numerical Three Dimensional Temperature Analysis Of The EGCR Fuel Rod

Description: The temperature field in an outer rod of the EGCR fuel assembly is presented. The numerical analysis has taken account of the three dimensional spatial dependence of the thermal neutron flux and has considered the four regions involved, that is, fuel pellets, ceramic disc, steel end caps, and cladding. The convective heat transfer coefficient and fluid temperature were considered constant over the 2.185 in. of rod length studied.
Date: March 21, 1960
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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Natural Circulation Burn Out Heat Flux For The ORR

Description: Natural circulation flow rate is calculated for the ORR core. From this flow rate, the burn out heat flux is found to be between 22,000 and 35,000 Btu/ft2-hr. It is concluded that under present conditions a positive acting after heat removal system is necessary for 30 mw operation.
Date: February 15, 1960
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
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Cladding Survey For The Enrico Fermi Reactor U-15 Wt % Mo Base Dispersion-Type Fuel Element

Description: Potential cladding materials for a flat-plate fuel element containing a dispersion of UC or UO2 in U-15 wt % Mo alloy were surveyed on the bases of compatibility with the fissile compounds, matrix material, protective cover materials, and liquid sodium as well as the feasibility of fabricating fuel plates by roll cladding.
Date: April 29, 1960
Creator: Martin, M.M. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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A Galvanic Corrosion Problem Associated With The Preparation Of Multimetallic Beryllium Samples

Description: Artifacts have been noticed in the microstructure of multimetallic beryllium samples that were polished on the Syntron vibratory polisher. These artifacts were at first erroneously attributed to diffusion of beryllium into the dissimilar metal. The real cause of the effect is thought to be due to a galvanic corrosion which takes place during polishing. Small additions of sodium nitrate to the polishing slurry have been found to eliminate the corrosion.
Date: April 20, 1960
Creator: Hewette, D. M.
Partner: UNT Libraries Government Documents Department
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Gamma And Beta Heat Generation Rates In The HFIR Core

Description: A calculation has been made to determine the fuel plate heat fluxes resulting from after shutdown fission product heating. Fission product source strengths were obtained via the IBM Internuc code. Slab geometry was assumed. The core coolant gamma heating rate during reactor operation has also been calculated using the same techniques, but including the fission and capture gamma sources.
Date: April 29, 1960
Creator: Hilvety, Neil
Partner: UNT Libraries Government Documents Department
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Corrosion In The Oak Ridge Research Reactor Core-Cooling System

Description: Corrosion specimens of the five major aluminum alloys used in the construction of the Oak Ridge Research Reactor have been exposed to the high-purity primary cooling water in the ORR core and in the external portion of the primary cooling loop to determine their corrosion rates under actual operating conditions. These alloys, 1100, 3003, 5052, 5154, and 6061, exhibited average corrosion rates of less than 2.6 mpy during the first 500-hr test period and less than 0.5 mpy for a 4032-hr test. Only… more
Date: April 25, 1960
Creator: Neumann, P. D.
Partner: UNT Libraries Government Documents Department
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Some Experiments On The Accuracy Of Thoria Slurry Samples

Description: Tests were performed on a thoria slurry flowing in a 3 inch diameter pipe to determine the magnitude of the possible error involved in the sampling process. Evidence indicates that a correct sample is obtained by withdrawing the sample isokinetically (i.e. by facing the sampler into the flow and adjusting the sampler velocity to match the ambient velocity) provided that the sampler is larger than some minimum diameter that is dependent on the mean eddy length and/or the mean particle size.
Date: April 21, 1960
Creator: Wichner, R. P.
Partner: UNT Libraries Government Documents Department
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Standard Operating Procedure For TSR-II

Description: The daily check list, the startup procedure both for in-pool and in-air operation, and the normal shutdown procedure for the Tower Shielding Reactor-II are outlined. The sequence of events which leads to each annunciator warning and the automatic corrective action which is then initiated by the control circuits are described.
Date: April 20, 1960
Creator: Lewin, J. S.
Partner: UNT Libraries Government Documents Department
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A Study Of The Fuel Value of U233

Description: The fuel value of U233 was calculated for five thermal reactors (Dresden, Yankee, Carolinas-Virginia, Hallam, OCR-II). Relative to a U235 value of $17 per gram, pure U233 had a value that varied from $18.2 to $20.2 per gram. U233 contained in once- and twice-recycle uranium from an initial U233-Th cycle value of U233 in recycle uranium from an initial U235-Th cycle was less than that for pure U233 and decreased with each succeeding cycle.
Date: April 11, 1960
Creator: Jaye, S.; Bennett, L. L. & Lietske, M. P.
Partner: UNT Libraries Government Documents Department
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An IBM 704 Subroutine For Trapezoidal Integration With Controlled Error (TRICE)

Description: An IBM-704 subroutine, TRICE, has been written in FORTRAN which evaluates a single integral by means of the trapezoidal rule approximation. In the calculational procedure, the integration step is halved until the desired degree of convergence is reached or until a preset maximum number of steps is exceeded. A maximum of ten different integrals may be used in any one calling program.
Date: April 19, 1960
Creator: Nestor, C. S.
Partner: UNT Libraries Government Documents Department
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GAP: The IBM 704 Grid Analysis Program

Description: GAP is an IBM 704 program for analyzing simply-supported rectangular beam grillages in which the beams intersect at right angles. The grillage need not be symmetrical and may have both uniformly distributed and concentrated loads. Also, the individual beams may have arbitrary cross sections. Strain energy methods are used to determine the bending, shearing, and torsional effects in a given grid structure. Deflections and moments can be found directly by the program, and series coefficients are … more
Date: May 2, 1960
Creator: Witt, F. J.
Partner: UNT Libraries Government Documents Department
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Desirability Of Chemical Decladding From The Waste Disposal Viewpoint

Description: Chemical decladding of stainless steel and Zircaloy jacketed fuel is discussed with respect to cladding activation, capacity for storage of decladding waste in existing concrete tanks at ORNL, and waste disposal cost as compared with a total dissolution process.
Date: April 1, 1960
Creator: Irvine, A. R.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report - April 1960, Chemical Technology Division

Description: Progress is reported on chemical engineering research, solvent extraction, fuel cycle development, thorium studies, ion exchange, reactor fuel processing, solvent extraction, and waste processing.
Date: July 28, 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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VPP -- Design Criteria For An Installation To Remove Hydrogen Fluoride And Fluorine From The Cells 1 And 2 Ventilation Gases Prior To Filtration

Description: Criteria are presented for a horizontal concurrent spray nozzle scrubbing system designed to remove fluorine and hydrogen fluoride from the 3000 cfm of ventilation air passing through the Volatility Pilot Plant located in cells 1 and 2, Bldg. 3019. A reduction of fluorine concentration from 1520 to <2 ppm during a total release of 68 lbs, and a reduction of hydrogen fluoride concentration from 4090 to <1 ppm during a total release of 200 lbs, will adequately protect the Fiberglass media filters… more
Date: April 11, 1960
Creator: Ruch, J. B.
Partner: UNT Libraries Government Documents Department
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