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Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States

Description: From Present Programs: "There has been a gradual expansion of the Sr^90 food analysis program to include vegetable foods and finally entire diets. In some cases the analyses have also been extended to other nuclides but these data are so limited that they will not be emphasized in this report. It is expected that considerable data on Ra^226 and other naturally occurring radionuclides will be generated in coming year."
Date: August 18, 1960
Creator: Harley, John H. & Rivera, Joseph
Partner: UNT Libraries Government Documents Department
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Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Partner: UNT Libraries Government Documents Department
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Military Field Expedient Shielding Experiment

Description: Convair-Fort Worth, under contract to the U.S. Army Engineer Research and Development Laboratories, performed experiments to obtain data for use in applying field materials to shield portable nuclear-reactor power plants.
Date: October 18, 1960
Creator: Wheeler, D. M. & Bostick, L. H.
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 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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Refueling-Core I, Seed 1-Disassembly Inspection of Control Rod Drive Mechanisms. Test Results T-643711

Description: An inspection was made of the drive mechanisms for corrosion, crud, pitting, and activity. Localized crud deposits were found in the L-5, F-12, and H-4 damper guide cup washers. Corrosion and pitting appeared slight. The gamma radiation level of the components ranged from 1 to 1900 mr/hr. Smear samples of the components indicated relatively low activity levels-the highest being 140 mr/ hr, gamma . The gamma emission spectrum for each smear sample showed the composition of all samples to be iden… more
Date: October 18, 1960
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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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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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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River Soundings. Core I, Seed 2. Test Results

Description: Water depth in the intake channel to the coolant-water screenhouse and surrounding area in the Ohio River near the intake channel were measured. From these measurements, the amount of silt removed during a previous dredging was determined. (C.J.G.)
Date: July 18, 1960
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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Effects of Irradiation on the Mechanical Properties of Tantalum

Description: Tensile, bend ductility, and hardness tests were performed at room temperature on irradiated tantalum sheet to determine the effect of irradiation on the strength and ductility. Sheet tensile specimens were irradiated in an attempt to produce corversions of tantalum to tungsten of approximately 1.5 and 3.0 wt.%. Unirradiated tantalum and arc-melted alloys of tantalum-1.5 and -3 wt.% tungsten were tested for comparison with the irradiated material. The tensile and yield strengths of tantalum wer… more
Date: November 18, 1960
Creator: Franklin, C. K.; Stahl, D.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
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A POTENTIOMETRIC STUDY OF ZIRCONIUM-NITRATE AND ZIRCONIUM-FLUORIDE SYSTEMS

Description: The potentiometric behavior of zirconium in fluoride, nitrate, and fluoride-nitrate systems is correlated and discussed in terms of the zirconium species present. A potentiometric titration was used successfully for the determination of total nitrate and zirconium in aqueous or organic (tributyl phosphate) zirconium-nitrate systems. (auth)
Date: August 18, 1960
Creator: Moffat, A. J.
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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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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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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Purification of mercury contaminated lithium hydroxide

Description: The object of this investigation was to determine an economical method of preparing pure lithium hydroxide from a mercury-contaminated lithium hydroxide monohydrate salt presently produced as a waste product. Pure lithium hydroxide has application for chemical removal of carbon dioxide from air and general open market sale if the mercury contamination is reduced to approximately one part per billion. Because of the uncertainty of the form of the mercury contaminant, different purification metho… more
Date: October 18, 1960
Creator: Bronfin, B. R.; Jenkins, D. M. & Wright, E. E. Jr.
Partner: UNT Libraries Government Documents Department
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