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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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Effluent system capacity Project CGI-883 increased process water flow -- 100-K

Description: The process water flow rates at the 100-K Reactors will be increased as a result of plant modifications under Project CGI-883. The flow rates to be achieved by the project are 188,000 and 200,000 gpm under five and six 190 Building pump operation respectively. Preliminary studies have indicated that the K-Area effluent systems will, for the most part, be adequate for the expanded conditions provided the reactor effluent is continuously and simultaneously discharged from two retention basis to t… more
Date: November 18, 1960
Creator: Schack, M. H.
Partner: UNT Libraries Government Documents Department
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Proposal to include blanket loadings in our plant improvement program

Description: Test metal was irradiated to simulate a `blanket` loading and striped E-N load under PT-IP-255-A-9-FP. The product analysis has now been obtained on the test material. The interpretation of this data and plant direction that might follow is considered in this document.
Date: November 18, 1960
Creator: Lang, L. W.
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
open access

Numerical results of production test IP-326-I, Low-flow calibration tests at B, D, F, and H Reactors

Description: Recent reviews of the last-ditch water backup system at the old reactors had shown that complete adequacy could not be demonstrated at all of the reactors under all conditions. However, these conclusions were based in part on conservative calculations using basic data with a sizeable amount of possible error. Subsequently, recommendations were made to run several tests which would increase the accuracy of the basic data and thereby allow an increase in the demonstratable level of last-ditch vat… more
Date: October 18, 1960
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
open access

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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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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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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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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Design of supplement B to PT-IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes

Description: One of the three major categories of HAPO fuel element failures is the side corrosion type rupture. The majority of side-corrosion failures has been characterized by oval or tear-drop shaped flow patterns containing evidence of accelerated corrosion. Thorough examination of many of these so-called `hot spot` failures has indicated the failure was caused by poor heat transfer associated with misalignment, dimensional distortion or poor jacket-to-core bonding. It has been postulated that misalign… more
Date: July 18, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
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
open access

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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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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A Spectrometer for Study of Neutron Activation of Beryllium-7 as a Function of Energy

Description: Abstract. A neutron diffraction crystal spectrometer with a resolution of 13 microseconds per meter and monochromatic beam intensity up to 10(4)n/cm(2)=sec in the range 0.012-0.400 ev has been constructed for study of the activation cross section of Be7 as a function of energy in the thermal region. First preliminary results using ZnS(Ag) as a detector suggest the possibility of a resonance for the Be7(n,p)Li7 reaction in the region of 0.025-0.050 ev.
Date: May 18, 1960
Creator: Boyer, Walton T., Jr.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report February 1960 - Chemical Technology Division

Description: Summaries of progress are presented for Fuel cycle development, GCR coolant clean up studies, HR Thorium blanket studies, Ion exchange, Power reactor fuel processing, Solvent extraction studies, Volatility, and Waste processing
Date: May 18, 1960
Creator: Whatley, M. E. (Marvin E.), 1926-; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
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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