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Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium

Description: Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Date: January 18, 1960
Creator: Billuris, G.
Partner: UNT Libraries Government Documents Department
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THE SNAP-II POWER CONVERSION SYSTEM. TOPICAL REPORT NO. 4. TURBINE DESIGN AND TESTING

Description: SNAP II is the designation for a 3 kw nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consist of a reactor heat source, a mercury Rankine engine, and an alternator. A two stage, full admission, axial flow turbine was chosen for this APU application. Design details and test results are presented. (auth).
Date: January 18, 1960
Creator: Poulos, E.N. & Furman, E.R.
Partner: UNT Libraries Government Documents Department
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The SNAP II Power Conversion System. Topical Report No. 4. Turbine Design and Testing

Description: SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date: January 18, 1960
Creator: Poulos, Earnest N. & Forman, Edward R.
Partner: UNT Libraries Government Documents Department
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Once Through Decontamination Studies- Interim Report No. 2

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.
Date: February 18, 1960
Creator: Hokenson, J. F. & Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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Quarterly Health Physics Report Through December 31, 1959 (Deleted Version)

Description: A resume of Health Physics activities for October, November, and December, 1959 is presented. Discussions and tabulations which summarize results of field surveys, bioassay, personnel monitoring, and environmental serveys are included.
Date: February 18, 1960
Creator: Meyer, H.E.
Partner: UNT Libraries Government Documents Department
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Radiometric Methods for the Determination of Magnesium and Calcium in Portland Cement

Description: Radiometric methods of analysis for magnesium and calcium have been developed as part of a program for the U. S. Atomic Energy Commission. Office of Isotopes Development, which are applicable to the determination of these elements in portland cement Both methods employ, as a precipitant, a standard solution of (NH/sub 4/)/sub 2/HPO/sub 4/ labeled with phosphorus-32. In the presence of NH/ sub 4/OH, this reagent precipitate; MgNH/sub 4/PO/sub 4/ or Ca/sub 3/(PO/sub 4/)/ sub 2/ from a solution of… more
Date: February 18, 1960
Creator: Brown, C. T.; Howes, J. E., Jr.; Elleman, T. S.; Townley, C. W. & Sunderman, D.N.
Partner: UNT Libraries Government Documents Department
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The Use of Ultrasonic in Electrodeposition and Electroplating : a Bibliography

Description: This bibliography contains 20 references on the use of ultrasonic in electrodeposition and electroplating. The bibliography is limited to the period 1955 to 1959, with the references arranged alphabetically by title. Sources used in compiling this bibliography were: Applied Science and Technology Index, ASM Review of Metal Literature, Chemical Abstracts, Industrial Arts, Index, Nuclear Science Abstracts.
Date: February 18, 1960
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in len… more
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Partner: UNT Libraries Government Documents Department
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Development of Thorium-Uranium-Base Fuel Alloys

Description: Thorium-uranium alloys were studied with the aim of developing alloys with improved irradiation behavior by control of microstructure. The effect of thorium purity, melting technique, hot and cold working, and heat treatment on microstructure was investigated. The most signifi- . cant microstructural differences occurred as a result of casting technique, The arc-melted alloys exhibited the most nearly ideal structure, that of a homogeneous dispersion of small-diameter uranium particles in a tho… more
Date: March 18, 1960
Creator: Farkas, Martin S.; Bauer, Arthur A. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
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MODIFIED ZIRFLEX PROCESS FOR DISSOLUTION OF 1-10% U-Zr ALLOY FUELS IN AQUEOUS NH$sub 4$F-NH$sub 4$NO$sub 3$-H$sub 2$O$sub 2$: LABORATORY DEVELOPMENT

Description: A modified Zirflex process was developed in the laboratory for dissolution of 1 to 10% uranium-zirconium alloy fuels to produce a nitrate solution from which uranium can be recovered by conventional solvent extraction methods. A flowsheet is presented for dissolution of 7% uraniumzirconium alloy in 5.4 M NH/sub 4/F-0.33 NH/sub 4/NO/sub 3/. Enough 1 M A/sub 2/O/sub 2/ is added continually during dissolution to yield 0.13 M H/sub 2/O/sub 2/ in the final solution, neglecting the amount reacting. D… more
Date: March 18, 1960
Creator: Gens, T.A.
Partner: UNT Libraries Government Documents Department
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Solids Separation by a Hydraulic Cyclone With a Batch Underflow Receiver

Description: >Engineering correlations based on experimental studies are presented for the application of batch accumulation of solids separated from solid-liquid feed to a cyclone. This method of cyclone operation simplifies the problem of flow control involved with continuous underflow. The efficiency and capacity correlations for hydroclones with continuous underflow also apply to this type of operation. The volume flow exchanged with the underflow receiver may be varied from 0.2 to 6% of the feed flo… more
Date: March 18, 1960
Creator: Haas, P. A.
Partner: UNT Libraries Government Documents Department
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Some Remarks On The Contribution Of Fission-Product Cesium To The Pressure Buildup In UO2 Fuel Elements

Description: The large fission yield of cesium and its apparent mobility in hot UO2 cause concern that it may contribute importantly to the pressure buildup inside clad fuel elements. A study has indicated that the pressure will essentially be that of metallic cesium and no significant addition will result from the formation of chemical compounds.The vapor pressure in a fuel element will be that associated with the coldest point accessible to the vapor.
Date: March 18, 1960
Creator: Rosenthal, M. W. & Cantor, S.
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF RADIOACTIVE FISSION PRODUCTS FROM POROUS FUEL ELEMENTS

Description: The release of fission products from porous fuel elements during irradiation may be largely a diffusion process. An equivalent-sphere hypothesis was proposed to provide a model by which the diffusion can be analyzed. The equations of diffusion were previously solved for in- pile conditions. The slow convergence of the formulas makes the previous solutions awkward. In the present investigation alternate formulas were derived which are more suitable under certain circumstances. Tables were prepar… more
Date: April 18, 1960
Creator: Beck, S.D.
Partner: UNT Libraries Government Documents Department
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Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly the transient cases. The question… more
Date: April 18, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Increased production study B, D, DR, F, H and C reactors

Description: This document studies a broad study program which is currently in progress in Irradiation Processing Department to evaluate the technical and economic feasibility of various methods of obtaining increased production from the six older reactors (B, D, DR, F, H, and C Reactors). Due to time limitations this study has been in general terms only, but has indicated that considerable increased plant return can be obtained from an increased conversion ratio as well as from higher reactor power levels.… more
Date: April 18, 1960
Creator: Fifer, N. F. & Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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Partial modification of 190-KW pump No. 1, Project CGI-883: Increased process water flow, 100 K

Description: The 190-KW process water pumping Unit No. 1 is scheduled to be modified for increased pumping capacity under Project CGI-883- Component parts for this modification are expected to-be received during June 1960. Installation of these components would require approximately ten days; due mainly to grinding of the high lift pump case to make room for the new larger diameter impeller. In order to minimize lost production, it has been proposed by K Reactor Operation that the high lift pump be modified… more
Date: April 18, 1960
Creator: Schack, M. H.
Partner: UNT Libraries Government Documents Department
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STUDY OF THE BETA TREATMENT OF URANIM. Progress Report to the Oak Ridge Operations Office for the Period November 1, 1959-April 1, 1960

Description: Activities in a program to determine the effects of product size (or dimensions), composition, and heat treatment on beta-treated U are reported. Progress to date was chiefly confined to organizing the program and setting up equipment. A Jominy end-quench apparatus was constructed, and preliminary experiments were run on as-cast metal to test the Jominy-oscillographthermocouple system. Results are tabulated. The method to be used for characterization of beta-treated samples by determination of … more
Date: April 18, 1960
Creator: Russell, R.B.
Partner: UNT Libraries Government Documents Department
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Existing reactor rear face piping review

Description: The rear face or discharge area of a reactor contains all the appurtenances necessary to discharge irradiated fuel, to collect hot coolant from each process tube, to monitor tube and effluent temperatures, and to monitor the coolant for ruptured fuel elements. Generally, failure of a rear face piping component would not affect the safety of the reactor since the coolant has fulfilled its purpose, that of cooling the fuel elements. The failure may, however, cause failure of one of the monitoring… more
Date: May 18, 1960
Creator: Fox, J. M. Jr.; Harrison, C. W.; Reinig, L. P. & Watson, D. F.
Partner: UNT Libraries Government Documents Department
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SAFEGUARD REPORT ON THE PROPOSED METHOD OF ANNEALING GRAPHITE IN THE X-10 REACTOR

Description: gone approximately 16 years of almost continuous irradiation. Throughout this time stored energy has accumulated at a slow rate to the present maximum value of about 35 cal/gm releasable to 250 deg C. A small portion of the moderator (approximately 4%) contains stored energy which under adiabatic conditions may be released spontaneously (at approximately 165 deg C) to produce a maximum temperature of 270 deg C. Careful analysis has shown that the presert condition is not hazardous; however, it … more
Date: May 18, 1960
Creator: Stanford, L.E.; Wittels, M.C.; Ramsey, M.E. & Cagle, C.D.
Partner: UNT Libraries Government Documents Department
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The Separation of Cerium from the Trivalent Rare Earths Using Hydrogen Peroxide and Sodium Acetate

Description: At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constitu… more
Date: May 18, 1960
Creator: Wheelwright, E. J. & Howard, N. C.
Partner: UNT Libraries Government Documents Department
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