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Fuel element handling before irradiation

Description: This report on fuel element handling presents in some detail the current status of an engineering study which has been underway for some time, and which is continuing. The study was undertaken to determine if it is feasible, and if it is practicable, to revise the method and equipment used for fuel element handling with existing charging machines.
Date: February 1, 1960
Creator: Gilbert, R. D.
Partner: UNT Libraries Government Documents Department
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CHANGE OF KEWB REACTOR CORES-EVALUATION OF SIGNIFICANCE WITH REGARD TO ASSOCIATED HAZARDS

Description: The KEWB Facility is described, and an over-all technical evaluation is made of the hazards associated with changing from a spherical to a cylindrical core. The characteristics of the two systems, the operation and emergency procedures, a brief history of the program, a summary of the data obtained, and maximum accident analyses are given. The conclusion is that the core change does not represent an adverse change with respect to associated hazards. (T.R.H.)
Date: February 1, 1960
Partner: UNT Libraries Government Documents Department
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The Drip Casting of Zirconium Metal. Work Completed: March 1951

Description: A drip casting process initiated to obtain zirconium castings uncontaminated by the melting process and to remove volatile impurities from the zirconium feed rod is described. A feed rod of zirconium is held above the mold, and the bottom of the rod is melted rapidly off into a mold to produce the casting. The melting process is carried out under high vacuum, so that very little atmospheric contamination can result, and some removal of volatile impurities is possible. Since no crucible is used … more
Date: February 1, 1960
Creator: Dunworth, R. J. & Macherey, R. E.
Partner: UNT Libraries Government Documents Department
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Transistor Scintillation Spectrometer

Description: The equipment described is an a-c operated portable scintillation spectrometer consisting of a preamplifier, a linear pulse amplifier, a single- channel pulse-height analyzer, a linear count-rate meter, a scaler, and a highvoltage power supply. The operation and performance of the circuits are discussed. The instrument is accurate and reliable, light in weight, and consumes low power. (auth)
Date: February 1, 1960
Creator: Strauss, M. G.
Partner: UNT Libraries Government Documents Department
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Numerical Solution of the One-Group Space-Independent Reactor Kinetics Equations for Neutron Density Given the Excess Reactivity

Description: The advantages and shortcomings of the codes currently in use at Argonne (RE-13 and RE-129) are discussed. A new method of solution, which has increased accuracy, stability for exceptionally large integration intervals, and a procedure for automatically changing the integration interval as the nature of the problem changes, is developed. (auth)
Date: February 1, 1960
Creator: Kaganove, J. J.
Partner: UNT Libraries Government Documents Department
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IMPROVED METHOD FOR PRECIPITATING MANGANESE DIOXIDE

Description: An improved method for precipitating manganese dioxide was demonstrated that significantly increases the allowable feed rate of the Purex head-end centrifuge. The effects of several process variables are discussed. (auth)
Date: February 1, 1960
Creator: Clark, H.J. Jr.
Partner: UNT Libraries Government Documents Department
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A versatile recording potentiometer

Description: ABS>A recording potentiometer was modified to provide a versatile instrument that can be applied to a variety of problems without time-consuming changes. Ranges may be selected in six spans, from 0.5 to 100 mv. No adjustments of amplifier gain are required when switching from one range to another. Zero suppression is continuously variable over a plus or minus 100 mv range by means of coarse and vernier controls. Cold junction compensation is provided for four standard thermocouples, and chart s… more
Date: February 1, 1960
Creator: Ballou, C. O.
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF KRYPTON-85 FROM URANIUM DIOXIDE POWDER

Description: The diffusion of Kr/sup 85/ in two UO/sub 2/ powders was studied by performing a series of post-irradiation anneals on the powders. The emanation data were analyzed by considering the effect of sintering as well as the effect of a distribution of particle sizes within the sample. Measurements were made at 900 to 1500 deg C. The time at a temperature was between 8 and 24 hours. The diffusion coefficients for Kr/sup 85/ in the two powders are represented by the equations: D = 2.65 x 10/sup -4/ ex… more
Date: February 1, 1960
Creator: Auskern, A.B.
Partner: UNT Libraries Government Documents Department
open access

THE INTERNAL FEEDBACK OF EBR-I MARK-III

Description: No Description Available.
Date: February 1, 1960
Creator: Carter, J. C.; Sparks, D. W. & Tessier, J. H.
Partner: UNT Libraries Government Documents Department
open access

Summary of Corrosion Investigations on High-Temperature Aluminum Alloys. Period Covered : February 1955-October 1956

Description: Tests were performed on aluminum alloys to evaluate their behavior in high-temperature, high-pressure. watercooled and -moderated nuclear reactor enviromnents. Test equipment, sample preparation. and test procedures are discussed. Aluminum nickel alloys were found resistant to disintegration for periods up to 60 days in dynamic water at 600 ction prod- F. The corrosion rates of the aluminum alloys M-388 and X-2219 at 600 ction prod- F were found to be too high to merit consideration for claddin… more
Date: February 1, 1960
Creator: Breden, C. R. & Grant, N. R.
Partner: UNT Libraries Government Documents Department
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The Catalysis of the Hydrogen-Oxygen Reaction by Aqueous Slurries of Thorium Oxide and Thorium-Uranium Oxide

Description: Aqueous slurries of thorium oxide and thorium oxide containing urarium were investigated for their catalytic activity for the reaction of hydrogen and oxygen to form water. Pure thorium oxide. thorium-uranium oxide mixed crystals prepared by calcining coprecipitated oxalates, and thorium oxide with uranium oxide sorbed on the surface were used after calcining at 650, 800, and 1000 deg . The reaction rates were found to be first order with respect to hydrogen pressure and zero order with respect… more
Date: February 1, 1960
Creator: Krohn, N. A.
Partner: UNT Libraries Government Documents Department
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Material Balance Flowsheets

Description: Material balance flowsheets are presented for the dissolution of UO/sub 2/, UO/sub 2/-ThO/sub 2/, and U-Mo fuels clad in stainless steel or zirconium by the Sulfex, Darex, and Zinflex process. The mechanics of the three processes are discussed. Basic assumptions upon which the flowsheets are based are contained. (auth)
Date: February 1, 1960
Creator: Shappert, L.B.
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, DECEMBER 1959

Description: Chemical-Metallurgical Processing. A direct-cycle pyrometallurgical fuel-processing plant is being constructed in conjunction with EBR-II. The gamma- irradiation testing of the 175-watt white fluorescent mercury vapor lamp was continued to an integrated exposure of 2 x 10/sup 9/ rad. Irradiation tests of Shell APL grease were completed, and the estimated useful life of this grease in the Air and Argon Cells is 2 and 3 years, respectively. Tests of the three - types of d-c motors used in the ope… more
Date: February 1, 1960
Partner: UNT Libraries Government Documents Department
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PROCESS FOR DISSOLUTION OF BORAX IV REACTOR FUEL: LABORATORY DEVELOPMENT

Description: Flowsheets are presented for the dissolution of Borax IV reactor fuel (6.35% UO/sub 2/)--ThO/sub 2/ pellets encased in 1% nickel--aluminum alloy and bonded with lead). In the preferred method the alurninum is dissolved first in boiling 2 M NaOH--1.78 M NaNO/sub 3/, with a urarium loss of approximately 0.07%. The lead and nickel are then dissolved in boiling 1.5 M HNO/sub 3/, with uranium losses of <0.2%. The oxide core is dissolved in two successive digestions with boiling 13 M HNO/sub 3/--0.04… more
Date: February 1, 1960
Creator: Ferris, L.M.
Partner: UNT Libraries Government Documents Department
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Anion Exchange Recovery of Plutonium From Reduction Residues

Description: An anion exchange process was demonstrated for the recovery of Pu from waste produced in the reduction of Pu salts to the metal. Pu in a highiy salted 6M nitric acid solution, derived from the dissolution of slag and crucible waste, was separated from impurities by absorbing the Pu(IV) nitrate complex on the anion exchange resin and subsequentiy eluting with dilute nitric acid. A flowsheet for plant operation is presented. (auth)
Date: February 1, 1960
Creator: Russell, E. R.
Partner: UNT Libraries Government Documents Department
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An Experiment to Measure Effective Delayed Neutron Fractions

Description: >An experimental measurement of the effective delayed neutron fraction ( beta -bar) was made for a clean critical assembly by determining the asymptotic period associated with introduction of a known amount of reactivity. The "known amount" of reactivity was obtained by replacing, uniformly throughout the reactor, a small quantity of U/sup 235/ with an alloy of B/sup 10/ and Hf designed to match the absorption properties of U/sup 235/. The replacement was thus equivalent to a uniform reduction … more
Date: February 1, 1960
Creator: Kaplan, S. & Henry, A. F.
Partner: UNT Libraries Government Documents Department
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Single tube meltdown incident

Description: In connection with design of rear face fittings for the plant-expansion study currently being conducted we have been asked to determine if rear face pressurization is required for safety reasons and if so, how much. Pressurization of the rear face piping would be used to provide sufficient reverse flow to prevent process tube burnout in the event of complete loss of coolant supply to a single tube by virtus of a front connector failure. Consideration of the effectiveness of rear face pressuriza… more
Date: February 1, 1960
Creator: Trumble, R. E.
Partner: UNT Libraries Government Documents Department
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EURIPUS-3 AND DAEDALUS--MONTE CARLO DENSITY CODES FOR THE IBM-704

Description: EURIPUS-3 calculates the one-dimensional spatial density of neutrons slowing-down past a given energy in an infinite homogeneous medium consisting of hydrogen and one other isotope with arbitrary mass and energydependent differential-elastic and absorption cross sections. DAEDALUS determines the corresponding spatial distribution of angular integrals of an arbitrary function times the vector flux density. Spatial moments of all density functions are furnished directly. Although scattering angle… more
Date: February 1, 1960
Creator: Amster, Harvey J.; Kuehn, Heidi G. & Spanier, Jerome
Partner: UNT Libraries Government Documents Department
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Interim Report -- The Retention of Particles in Ducts Transporting Aerosol Streams

Description: Accurate sampling of particulate in gaseous effluents is required for auditing and control of radioactive wastes released to the environment at installations generating or processing radioactive materials. Over the years a variety of sampling probe configurations, sampling velocities, lengths and sizes of sample delivery lines have been used locally to obtain these samples. Efforts to properly evaluate the validity of samples in most sampling installations have been hampered by a lack of basic … more
Date: February 1, 1960
Creator: Postma, A. K. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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