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Aerospace Safety Re-Entry Analytical and Experimental Program, SNAP 2 and 10A (Interim Report)

Description: Before a reactor is launched into a satellite orbit about the Earth, the hazards to the population must necessarily be considered in the event that the reactor re-enters the Earth' s atmosphere and possibly impacts with the ground. Analytical and experimental efforts for calculating these potential hazards as they apply to SNAP-2 and -10A are described. (auth)
Date: September 30, 1963
Creator: Elliott, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the Babcock and Wilcox Full-Size Steam Generator for a Sodium-Water Reaction

Description: An analysis of the effects of a sodium-water reaction in The Babcock & Wilcox Full-Size Steam Generator was conducted. A leak in a tube of the unit would cause a sodium-water reaction which would result in the rapid generation of quantities of reaction products, including hydrogen and high temperature
Date: November 30, 1965
Creator: Chase, W.L.; Ford, J.A.; Friedland, A.J.; Green, D.M.; Kovac, L.R. & Meyers, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs

Description: A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods… more
Date: January 30, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of Nuclear Power Supplies to Space Systems

Description: Studies were made to ascertain what useful satellite and/ or space missions may be accomplished with the SNAP 2, 8, and 10 power systems within the 1960 to 1970 time period, to delineate useful satellite and/or space missions which would most profitably employ nuclear power sources, to ascertain what restrictions are imposed on various payloads as a result of having a nuclear power system on board, and to investigate the general vehicle integration and installation requirements of the SNAP 2 an… more
Date: June 30, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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APPLICATIONS OF SNAP REACTOR SYSTEMS TO COMMUNICATIONS SATELLITES

Description: Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)
Date: July 30, 1962
Creator: Wimmer, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SUMMARY REPORT ON MATERIALS FOR THE GCRE-II

Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear … more
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Blisters in BDF-type control rods: Engineering final summary report

Description: The scope of this report defies a concise abstract. In lieu of an abstract, the following topical outline will both indicate the subjects covered and show how these subjects are organized. Part I, Engineering Aspects: Blister Formation, Temperature Effects, Cooling Effects, Drive Connections, Housing Effects, Housing Materials, Radiation Effects. Part II, The Behavior of Boron Carbide-Aluminum Poisons: Swelling, Swelling Rates, Restraint, Material Behavior.
Date: August 30, 1965
Creator: Riedeman, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Budget for FY 1971 and revision of FY 1970 Douglas United Nuclear, Inc. , 02 research and development

Description: The Richland 02 Five-Year Process Development Program has been divided into 10 missions. The missions by title were: Basic Production; Coproduct; Transplutonium; Pu-238; Other Isotopes; Enriched Fuel Processing Target Space Enhancement Nuclear Safety; Waste Management; and Columbia River Studies. Although in general most of the same efforts are incorporated, the mission concept is being dropped, and the following designations for programs have been adopted: Basic Production; Product Flexibility… more
Date: April 30, 1969
Creator: Ambrose, T. W. & Riches, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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C reactor overbore fuel failures

Description: The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.
Date: April 30, 1962
Creator: Ambrose, T. W. & Graves, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CASPER: A Generalized Program for Plotting and Scaling Data

Description: A Fortran subroutine was written to scale floating-point data and generate a magnetic tape to plot it on the Calcomp 570 digital plotter. The routine permits a great deal of flexibility, and may be used with any type of FORTRAN or FAP calling program. A simple calling program was also written to permit the user to read in data from cards and plot it without any additional programming. Both the Fortran and binary decks are available. (auth)
Date: January 30, 1963
Creator: Lietzke, M.P. & Smith, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, July 1961

Description: Thoria denitrator products from 0.04 to 0.066 N/Th ratio were dispersed into sols at N/Th radios of 0.11 to 0.19 and processed by the sol-gel technique to produce final compacted thoria products with little significant variation. Experimental results of H/sub 2/-CuO reaction in the helium purification work further substantiated the mathematical model. The elutions of uranyl sulfate loaded Dowex 2lK with chloride apparently involved the diffusion of both the sulfate ions and the uranyl ions. The… more
Date: January 30, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program; Aircraft Nuclear Propulsion Application Studies

Description: This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This portion describes the studies of advanced applications of nuclear reactors that were performed, including various types of aircraft, missiles, space vehicles, ships, and portable power plants.
Date: April 30, 1962
Creator: Comassar, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conoseal Bar-X Seal Tests

Description: On the NRX-A reactors the instrument ports are sealed by a Bar-X seal. Damage to the ports, which are part of the pressure vessel, required machining on the pressure vessel. A new design, using a Marman flanged piece to house the Bar-X seal port separate from the pressure vessel, was proposed. The test program was to determine the torque required to seal and the ability of each seal to hold during thermal shock.
Date: November 30, 1964
Creator: Edmiston, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Containment of Iodine-131 Released by the Rala Process

Description: Uncontrolled releases of large amounts of iodine occurred during the early stages of RaLa operation at the ldaho Chemical Processing Plant. A ten- fold reduction in the iodine content of the off-gas was achieved by process modifications, primarily the addition of mercury salts to the acidic process solutions. An additional ten-fold reduction was obtained by installing an activated charcoal adsorption unit in series with the original iodine removal scrubber. The iodine content of particulate ent… more
Date: October 30, 1961
Creator: Cederberg, G. K. & MacQueen, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Studies for a Fused Salt-Liquid Metal Extraction Process for the Liquid Metal Fuel Reactor

Description: Corrosion screening tests were carried out on potential materials of construction for use in a fused salt-liquid metal extraction process plant. The corrodents of interest were NaCl--KCl-- MgCl/sub 2/ eutectic, LiCl--KCl eutectic, Bi-- U fuel, and BiCl/sub 3/, either separately or in various combinations. Screening tests to determine the resistance of a wide range of commercial alloys to the corrodents were performed in static and tilting-furnace capsules. Some ceramic materials were tested in … more
Date: June 30, 1960
Creator: Susskind, H.; Hill, F. B.; Green, L.; Kalish, S.; Kukacka, L. E.; McNulty, W. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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