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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.
Partner: UNT Libraries Government Documents Department
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STUDIES OF THE SCINTILLATION PROCESS IN CsI(Tl)

Description: The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, specia… more
Date: November 30, 1962
Creator: Gwin, R. & Murray, R. B.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 2, December 15, 1961 to March 14, 1962

Description: The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it… more
Date: March 30, 1962
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

Description: S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Partner: UNT Libraries Government Documents Department
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Stress Analysis of the SM-1A Reactor Vessel

Description: The stress analysis performed on the SM-lA reactor vessel and cover is presented. The msximum combined stress (51,360 psi in compression) occurs in the vessel cover during a 50 deg F/hr transient. A fatigue analysis of these stresses indicated that they could be applied safely at least 2500 times, and since the vessel is expected to receive less than 900 cycles, it should not suffer any fatigue damage. (auth)
Date: March 30, 1962
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Partner: UNT Libraries Government Documents Department
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Process Development and Fabrication of PbTe Thermoelectric Elements

Description: The development and fabrication of Pb-Te pellets, contacted to Fe end caps, for use as elements in thermoelectric converters for the SNAP 10A program, is described. The method adopted consists of contacting, by hot pressing in a controlled atmosphere, 24 pellets simultaneously, using q-layer, 8-cavity graphite dies. The optimum hot pressing parameters were found to be 5000 psi at 1550 deg F for 30 min. Several thousand elements were produced by this relatively high-volume process, modifying the… more
Date: October 30, 1962
Creator: Bennett, F. R. & Langrod, K.
Partner: UNT Libraries Government Documents Department
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An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels. Part I. Preliminary Laboratory Studies

Description: The expanding use of Zircaloy-clad Zr-enriched U alloy fuel suggested a need for higher capacity reprocessing facilities. The most ungent requirement is for continuous dissolution equpment to match the solvent extraction capacity already available at Idaho Chemical Processing Plant. Because of the rapid disaolution rates possible with aqueous HF on clean metal as well as on oxidized fuels, and subsequent flowsheet economics, it is the reagent of choice. Laboratory measurements and a survey of t… more
Date: October 30, 1962
Creator: Rohde, K. L.; Newby, B. J.; Paige, B. E.; Roeh, A .P,; Hoffman, T. L. & Decker, L. A.
Partner: UNT Libraries Government Documents Department
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A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

Description: From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 2, December 1961 - March 1962

Description: Abstract: "The purpose of this investigation is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 have been hydrogenated to 200 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture has been observed which can be attributed t… more
Date: March 30, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Boiling Potassium Heat Transfer Project Loop Design and Development

Description: This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.
Date: April 30, 1962
Creator: Chen, John C., 1934-2013
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.
Partner: UNT Libraries Government Documents Department
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Performance test, Additional pumping capacity, 181-D

Description: The existing pumping capacity and piping intertie arrangement between 181-D and 183-DR makes it necessary to continuously cross-feed treated water from 183-DR flumes to insure adequate reactor flow to 105-DR to meet present production levels. This arrangement means that pumping equipment in both 181-D and 183-D is kept in use to the extent that repair or productive maintenance work must be accomplished during reactor outages, or production levels must be reduced to release a pumping unit during… more
Date: October 30, 1962
Creator: Hedges, J. W.
Partner: UNT Libraries Government Documents Department
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Progress in reactor water plant operation, FY 1958--FY 1962

Description: The water plants and associated steam back-up facilities which supply coolant to Hanford`s eight production reactors are large and vital facilities. Their reliability is essential to the safety and continuity of reactor operation. Their output and efficiency are important to reactor productivity and to the unit cost of plutonium and other irradiation products. In the fiscal year just ended, the cost of operating the reactor water and steam plants was $16,000,000, which represented a major fract… more
Date: July 30, 1962
Creator: Hauff, T. W. & McDougal, P. G.
Partner: UNT Libraries Government Documents Department
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Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Description: Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.
Date: June 30, 1962
Creator: Chittenden, W. A. & Hoveke, G. F.
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.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Meeting: March 1962

Description: A report regarding proceedings of the nuclear superheat meeting no. 6, held March 7, 8 and 9, 1962, in Windsor, Connecticut.
Date: March 30, 1962
Creator: Mravca, Andrew E.
Partner: UNT Libraries Government Documents Department
open access

Thermal Analysis of Type 3 Elements in the SM-1, SM-1A and PM-2A Cores

Description: Report describing a study which analyzed thermal characteristics of Type 3 elements planned for installation in the SM-1, SM-1A and PM-2A plants, for both steady state and loss of flow transient conditions. Results of this analysis for steady state conditions indicate that the SM-1, SM-1A and PM-2A Type 3 cores will operate safely at design and scram conditions.
Date: March 30, 1962
Creator: Davidson, S. L. & Segalman, I.
Partner: UNT Libraries Government Documents Department
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An Economic Evaluation of Ultimate Disposal of Liquid Radioactive Wastes by the Fluidized Bed Calcination Process

Description: The costs of fluidized bed calcining of the acidic and re-acidified forms of Purex and Thorex wastes were determined. The wastes were assumed produced by a chemical-processing plant recovering unburned fuel from 1500 tons/ yr of U converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/yr of Th converter fuel at 20,000 Mwd/ton. Also, investment costs for storage of the calcine in vented, air cooled, annular bins installed in underground concrete valuts were determined. The cost of fluidized b… more
Date: October 30, 1962
Creator: Stevens, J. I.
Partner: UNT Libraries Government Documents Department
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