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CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III

Description: A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phase… more
Date: October 1, 1962
Creator: Branyan, C.E.
Partner: UNT Libraries Government Documents Department
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Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2

Description: Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch… more
Date: October 1, 1962
Creator: Prislinger, J. J.
Partner: UNT Libraries Government Documents Department
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Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks

Description: Thermal-stress and strain-fatigue analyses of the MSRE fuel and coolant pump tanks were completed for determining the quantity of coollng air required to obtain the maximum life of the pump tanks and to determine the acceptability of the pump tanks for the intended service of 100 heating cycles from room temperature to 1200 deg F and 500 reactor power-change cycles from zero to 10 Mw. A cooling-air flow rate of 200 cfm for the fuel pump tank was found to be an optimum value that provided an amp… more
Date: October 1, 1962
Creator: Gabbard, C.G.
Partner: UNT Libraries Government Documents Department
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ARGONNE NATIONAL LABORATORY PUBLICATIONS, JULY 1, 1961-JUNE 308 1962

Description: A publications list, incorporating a subject index was compiled by machine methods. The publications covered are those originating at Argonne but published elsewhere. The list is arranged alphabetically by author's names and covers the period from July 1, 1961 through June 30, 1962. The subject index is a key word in context index using the title. (M.C.G.)
Date: October 1, 1962
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, April 1962

Description: Bubble size measurements in the foam column showed that a spinnerette with 50 mu holes gave a nearly normal distribution of bubbles sizes while a coarse fritted glass gas sparger had a tail of large bubbles which did not fit the normal curve. A set of equations solvable by a finite difference technique are presented which completely describe the irreversible reaction rate of H/sub 2/ or CO with a fixed bed of CuO pellets. Radiation damage tests are in progress to evaluate plastics for the Trans… more
Date: October 1, 1962
Creator: Whatley, M. E.; 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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PREPARATION OF STOICHIOMETRIC URANIUM MONOCARBIDE CYLINDERS

Description: Employing a modified arc-melting technique, homogeneous cylinders of stoichiometric UC were consistently produced. The cylinders ranged in size from 0.25-in. dia. by 1 in. long to 0.375-in. dia. by 3 in. long. The top 10% of nearly all cylinders did, however, contain shrinkage voids that could not be eliminated. UC buttons previously prepared by arc melting the elements were placed over a graphite-mold cavity, but in contact with Cu in an Aratmosphere arc furnace. When the UC charge became full… more
Date: October 1, 1962
Creator: Bourgette, D.T.
Partner: UNT Libraries Government Documents Department
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Presentation to the Atomic Energy Commission and the Air Force, June 14, 1962

Description: This volume contains the charts and backup material presented to the Atomic Energy Commission and Air Force on June 14, 1962 concerning General Electric's Nuclear Materials and Propulsion Operation (formerly the Aircraft Nuclear Propulsion Department), during its work on the development of a nuclear power plant for manned aircraft.
Date: October 1, 1962
Partner: UNT Libraries Government Documents Department
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Automatic Foil Activity Counting Facility and Data-Reduction Program

Description: A transistorized automatic counting and recording system was built for the determination of foil-activation data. Output data are on IBM-printed and punched cards which may be processed by a high-speed computer. The computer produces tabular and graphical output, as well as punched data cards which may be used for further processing such as curve fitting. The foil-activation data are taken from one to six chains operating in unison (normally samplechanger, detector, amplifier, analyzer, scaler,… more
Date: October 1, 1962
Creator: Plumlee, K. E. & Wiggins, M.T.
Partner: UNT Libraries Government Documents Department
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Mathematics of Intermittent Irradiation

Description: Initiation of reactions by intermittent irradiation is frequently encountered in physical, chemical, and biological systems. Mathematicai expressions for transient and steady state concentrations of reactive species in these systems are useful for predicting performance and for research purposes. A general method of formulation of the intermittent irradiation problem is presented herein, and illustrative solutions are obtained for radioactive decay chains and for the rotating sector method. 20 … more
Date: October 1, 1962
Creator: Hill, F.B.
Partner: UNT Libraries Government Documents Department
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Contribution to the Theory of Two-Phase, One-Component Critical Flow

Description: Equipment was built where critical-flow data above 100 psia were obtained and a theory developed that predicts the experimental values satisfactorily. Theoretical expressions for the specific volume, void fraction, and slip ratio for critical steam-water mixtures have been derived. Therefore, the first complete analytical solution was made possible for estimating the critical two-phase flow rate, including slip between the two phases. The pressure profiles for runs at critical flow were all cha… more
Date: October 1, 1962
Creator: Fauske, H. K.
Partner: UNT Libraries Government Documents Department
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Ejecta Studies

Description: One-hundred and forty-six ejecta measurement stations encircled ground zero at eight radial distances ranging from 373 to 1707 meters. The twenty-four sampling lines were spaced at fifteen-degree intervals. Data presented were recovered from stations located at radial distances of 640, 853, 1067, 1280, and 1707 meters. An attempt will be made to recover data at stations located closer to ground zero at a later time. Preliminary analysis of ejecta data indicates that areal density varies inverse… more
Date: October 1, 1962
Creator: Roberts, W. A. & Carlson, R. H.
Partner: UNT Libraries Government Documents Department
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SURFACE AND VOLUME PROPERTIES OF GROUND STATE NUCLEAR MATTER IN THE HARTREE- FOCK AND PUFF-MARTIN APPROXIMATIONS

Description: ABS>A method was derived for computing the ground state properties of a spatially inhomogeneous self-bound system of many particles. This method was used to compute the density and effective potential across a plane surface of nuclear matter in the Hartree-Fock approximation and in an approximation developed by R. D. Puff and P. C. Martin which takes into account certain two- body correlation effects. A general theory of many-particle systems was developed in terms of the n-particle field corre… more
Date: October 1, 1962
Creator: Reynolds, J.C.
Partner: UNT Libraries Government Documents Department
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Tunnel Diode Circuit Analysis

Description: Graphical and graphico-analytic methods were applied to the most common tunnel diode circuit configurations. The isocline method and a useful generalization of the Lienard Method were developed and applied, solutions and stability criteria were obtained by singular point analysis, and methods using linearized characteristics or simple graphical operations were applied. (auth)
Date: October 1, 1962
Creator: Roddick, R.G.
Partner: UNT Libraries Government Documents Department
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Results of Tensile Tests Performed on Materials Exposed in the Homogeneous Reactor Experiment No. 2 Blanket and Low-Flux-Core Region

Description: Tensile specimens of various alloys of zirconium and titanium and a variety of austenitic stainless steels and Incoloy were exposed in the blanket and low-flux core regions of the Homogeneous Reactor Experiment (HRE) No. 2. The purpose of this exposure was to determine the effect of HRE-2 environment on mechanical properties and to provide corrosion data. Specimens were exposed in the low-flux core region and in two blanket loadings. While the specimens were in the low-flux core region, a maxim… more
Date: October 1, 1962
Creator: Prislinger, J. J.
Partner: UNT Libraries Government Documents Department
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A STUDY OF URANIUM-FISSIUM ALLOYS CONTAINING TECHNETIUM. Addendum to Final Report--Metallurgy Program 4.1.23

Description: The equilibrium microstructures and the kinetics of gamma decomposition of uranium-fissium alloys containing technetium were studied and compared with the characteristics of similar alloys which did not contain technetium. The technetium concentration in the fissium was 12.5 wt% and the uranium-fissium alloys that were examined contained from 3 to 10 wt% fissium. The presence of technetium did not result in the presence of any new phases; it produced only minor changes in the phase relationship… more
Date: October 1, 1962
Creator: Bohl, R.W. & Nevitt, M.V.
Partner: UNT Libraries Government Documents Department
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THE SNAP II POWER CONVERSION SYSTEM. TOPICAL REPORT NO. 17. MERCURY BOILING RESEARCH

Description: Activities in a boiling research program to provide data on heat transfer and pressure drop during vortex oncethrough forced convection boiling of Hg are reported. A test rig was built for test section configurations with swirl wire inserts; or in one case, a bare tube. Efforts were made during the testing of one swirl wire test section to obtain data on the independent effect of temperature difference, pressure level, flow rate, and quality level on heat transfer rate. The data are correlated … more
Date: October 1, 1962
Creator: Gido, R.G. & Koestel, A.
Partner: UNT Libraries Government Documents Department
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INSTRUMENTED TEMPERATURE-CONTROLLED CAPSULES FOR IRRADIATIONS IN THE CP-5 REACTOR

Description: Instrumented, temperature-controlled irradiation capsules are being operated in the vertical fuel tubes of the CP-5 test reactor. The fuel tubes were modified in order to divert reactor coolant into the tubes to cool the capsules, and the shield plugs were revised to accommodate the capsule assemblies. Fuel materials and structural materials were successfully irradinted for periods in excess of one year. A description is included of the present capsule and assembly, the method of temperature co… more
Date: October 1, 1962
Creator: Beck, W.N. & Fousek, R.J.
Partner: UNT Libraries Government Documents Department
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