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13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8

Description: Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Date: August 1, 1960
Creator: Bloom, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ANNUAL SUMMARY RESEARCH REPORT IN ENGINEERING FOR JULY 1, 1959-JUNE 30, 1960

Description: Work was continued on the determination of size and distribution of dispersed phase droplets in a pulse column. The droplet behavior and dispersed phase hold-up in Yorkmesh packing was studied with an equilibrated system of methyl isobutyl ketone and water with the ketone phase dispersed. An investigation is being made of the recovery of copper and EDTA from rare-earth ion exchange wastes. The effect of vapor properties on entrainment from bubble cap trays is being investigated. The design, con… more
Date: August 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bibliography of SNAP Reports

Description: A listing is presented of documents, films, slides, and those items which were formally produced for utilization by the AEC concerning the SNAP project. (J.R.D.)
Date: August 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for July 1960

Description: Production of Pu nitrate from separations plant during this month was below forecast. UO{sub 3} production, shipments met schedules; so did unfabricated Pu shipments. Purex plant was stopped to replace the final waste concentrator (F-11) (leak). Two Pu-U partition failures were attributed to foreign organic material in the nitric acid; the Pu product was kept within specifications by adding NaF and ANN to ion exchange feed stream. A Np recovery run was started in Redox, and dissolution was star… more
Date: August 22, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part I. Summary of Technical and Economic Status as of 1960. Heavy Water-Moderated Power Reactors

Description: A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel de… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part III. Status Report on Large (100 and 300 MWe) Heavy Water-Moderated Power Reactors--as of 1960

Description: An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce powe… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coherent Electromagnetic Effects in High-Current Particle Accelerators: [Part] 3. Electromagnetic-Coupling Instabilities in a Coasting Beam

Description: The electromagnetic interaction of an intense relativistic coasting beam with itself, including the effect of a confining nonperfect vacuum tank, or a quiescent rf cavity, is investigated theoretically. It is shown that the resonances that may occur between harmonics of the particle circulation frequencies and the electromagnetic modes of the cavities can lead to a longitudinal instability of the beam. A criterion for stability of the beam against such longitudinal bunching is obtained as a res… more
Date: August 4, 1960
Creator: Laslett, L. J.; Neil, V. Kelvin & Sessler, A. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Compilation of Room Temperature and 1200 F Properties of Metallic Materials With Specific Reference to Their Use as Fuel Cladding in Sodium Cooled Thermal Reactors

Description: A compilation is presented of room temperature and 1200/sup o/F properties of a large number of alloys which might be considered for use in a sodium-cooled reactor. Specific consideration is given to the use of such materials as fuel cladding. The arbitrary basis for property comparison is type 304 stainless steel. The study was made of 10 classes of alloys. These alloys are alloy steels, ferritic stainless steels, austenitic stainless steels, iron and iron-aluminum alloys, precipitation-harden… more
Date: August 16, 1960
Creator: Kline, H.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coolant backup design study basis and objective

Description: Preliminary studies have, in general, indicated the need for modifications and improvements to the reactor last ditch coolants systems in order to provide adequate safety of operation at power levels programmed for the future. These studies have indicated the need for improved reliability as well as increased capacity for the last ditch coolant systems. A design study is being prepared by Reactor Modification Design to define the scope of the modifications required to provide adequate last ditc… more
Date: August 31, 1960
Creator: Schack, M. H. & Tupper, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CREEP AND CORROSION PROPERTIES OF ZIRCALOY-2 IN STEAM AT 750 F

Description: Test equipment to determine the creep properties of Zircaloy-2 in a 750 deg F 500-psi steam atmosphere was designed and constructed. Duplicate tests were performed at stresses to produce failure in approximately 1, 10, 100, and 1000 hr. A comparison between these data and data obtained in vacuum-test equipment showed that a corrosive test atmosphere does not alter ductility or failure times appreciably. (auth)
Date: August 1, 1960
Creator: Jablonowski, E. J. & Shober, F. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of production test IP-344-A-FP, determination of the limitations of the Al-Si process

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can bond separation following irradiation. Such evidence h… more
Date: August 31, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Fuel-Element Leak-Detection System Based on the Principle of Isotopic Exchange

Description: The selective removal of halide fission products from an aqueous solution by exchange with the halide in a solid silver halide was studied as the basis for a fuel-element leak detector. The retention of fission-product halides on a silver halide column was investigated as a function of coolant flow rate, halide anion, and column size. Fission prcduct decontamination factors and predicted operating lifetimes were obtained for a number of reactor operating conditions. It is concluded that a sensi… more
Date: August 1, 1960
Creator: Howes, J. E., Jr.; Elleman, T. S. & Sunderman, D. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Corrosion-Resistant Alloys for Use as Container Materials for Decladding Solutions or as Welding Alloys

Description: Twenty-four experimental alloys were developed and evaluated as container materials or welding alloys for use with Sulfex and Niflex decladding solutions. Niflex solutions which were more corrosive than Sulfex solutions to most of the experimental alloys, produced severe localized attack on weldments made on vacuum-melted Hastelloy F with the experimental alloys. However, several of the alloys, when self-welded, were not selectively attacked. Some of these showed a substantial improvement in re… more
Date: August 1, 1960
Creator: Peterson, Charles L.; Drennen, David C.; Langston, Merritt E.; Hall, A. M. & Boyd, Walter K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Electron Multiplier as a Detector for a Surface Ionization Mass Spectrometer--Design

Description: A description of a 14-stage electron multiplier for use amplifying the detector signals in a surface ionization mass spectrometer is given. The system can either measure the multiplier anode current or count the anode pulses. Pulse counting may be used for- signal currents in the range from lO/sup -13/ to 10/sup -18/ amp. The range of the normal electrometer circuit is extended by the electron multiplier so that it measures currents from l0/sup -10/ to 10/sup -15/ amp with a fast response. (aut… more
Date: August 1, 1960
Creator: Cathey, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Gas Cooled Reactor-Creep Test, Agot Graphite

Description: Tests were conducted to determine the cumulative and permanent deflection of a beam subjected to two-point loading for (1) ambient temperature- atmospheric environment, and (2) 800 deg F-atmospheric environment, for 8OO psi maximum flexural stresses. Deflection curves are given for five specimens. An analysis of the data indicated that if the core graphite creeps while at EGCR conditions by approximately 1.5 times its creep rate at ambient temperature, the stresses will level off below 1000 psi… more
Date: August 23, 1960
Creator: Lain, P. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FUEL TEST REACTOR-FFTR CONCEPTUAL DESIGN STUDY

Description: The Fast Fuel Test Reactor (FFTR) is a nuclear facility for the purpose of irradiating samples of fuels and structural components for use in fast reactors. The core consisis of a plate type element in a square configuration. Beryllium metal between the fuel elements is used to obtain a neutron energy spectrum in the hard intermediate region. Cooling of the core and test specimens is accomplished by means of liquid sodium. The design concept was carried through in sufficient degree in the follow… more
Date: August 1960
Creator: Brubaker, R.; Hummel, H. H.; McArthy, A.; Smaardyk, A. & Kittel, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FISSION-GAS-RELEASE FROM UO$sub 2$, INTERIM REPORT NO. 1

Description: The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of primary interest to the Gas-cooled Reactor Project. Fuel tests consisting of UO/sub 2/ pellets encapsulated in Inconel or stainless steel were irradiated in the LITR, ORR, and ETR. The capsules were pierced in hot cells, and the gases collected in evacuated systems. Fractions of this gas, of suitable activity for counting, were taken and then analyzed by gamma spectrometry. Larger fractions of gas wer… more
Date: August 16, 1960
Creator: Morgan, J. G.; Morgan, M. T. & Osborne, M. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Fluorination of Uranium From Dried Solids and Its Application to the Fluoride Volatility Process

Description: The fluorination of uranium from dried solids representative of those obtained from the fluid-bed drying of dissolver solutions of high zirconium alloy fuels. e.g.. Dresden and Army Package Power Reactor fuels, was studied under a variety of conditions. Variables investigated were particle size, additives, temperature, time. hydrofluorination, and pyrolysis. Temperatures in excess of 650 deg C were needed to ensure complete removal of uranium from the solid. Pyrolysis with HF of previously fluo… more
Date: August 1, 1960
Creator: Johnson, C. E. & Fischer, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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