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Betatron Oscillations and Equilibrium Orbits in Terms of Amplitude and Phase Functions

Description: "Formulas are given to express the general particle trajectory and the equilibrium orbit for a slightly disturbed synchrotron in terms of the amplitude and phase functions for the ideal machine. If these functions are known, orbit computations can be carried out by simple integration procedures. The formalism is expected to be useful especially for considerations such as beam alignment or generation of an external electron beam. Some equations given earlier are repeated for completeness."
Date: January 7, 1958
Creator: Steffen, K. G.
Partner: UNT Libraries Government Documents Department
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Main Coolant Pump Performance Test. Section I. First Performance. Core I, Seed 1. Test Results DL-S-290, T-641326

Description: The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.
Date: December 7, 1959
Creator: Edwards, Gerald E.
Partner: UNT Libraries Government Documents Department
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Examination of Components for Crud and Corrosion. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-155, T-612080

Description: The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 223… more
Date: December 7, 1959
Creator: Muldoon, James B.
Partner: UNT Libraries Government Documents Department
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The Shape of a Shock Wave Derived from a Spherical Shock Wave Incident on a Concave Wedge

Description: When a one-half ounce spherical charge of high explosive is detonated over a flat plane bounded by a 5 degree incline, the type of phenomenon encountered depends on the distance from ground zero to a beginning of the incline. If this distance is 48" the wave assumes a smooth contour on the plane. Detailed investigation of the shock velocity above the plane reveals that there is a pressure gradient along the shock front for a considerable region which replaces the usual triple point.
Date: July 7, 1954
Creator: Todd, Jay, Jr. & Schellenbaum, Ralph L.
Partner: UNT Libraries Government Documents Department
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Practical Methods for the Reduction of Strain Gage Data

Description: The error that results when it is attempted to evaluate stress from a reading taken on a single element SR-4 strain gage in a biaxial stress field is discussed. A method is presented for relating SR-4 rosette strain gage readings directly to the biaxial stress state without the necessity of first converting strain gage readings to true strains. Correction formulas are presented for use when single element SR-4 gages are used as rosette elements or as stress gages.
Date: September 7, 1955
Creator: Dove, Richard C.
Partner: UNT Libraries Government Documents Department
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Analytic Approach for the Pion-Proton Scattering Phase Shifts

Description: A simple method of solving for the phase shifts of the pion-proton scattering is presented. The rapid solution afforded can be utilized, as the Ashkin diagrams have been employed, to give starting values to an electronic computer or alternatively to analyze with more ease the variation of the phase shifts as a function of the input data in terms of the coefficients of the angular distributions. A new plot of a function of the total cross section versus the pion energy is introduced. The nearly … more
Date: December 7, 1955
Creator: Rarita, William, 1907-
Partner: UNT Libraries Government Documents Department
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The Helium Purification System for the Proposed 800 MWT Pebble Bed Reactor

Description: A helium coolant purification system was designed for the proposed 800 MWT Pebble Bed Reactor. The purification system will operate on a coolant side stream with a flow rate 1% of the total coolant flow and there are provisions for radioactive and non-radioactive contamination removal.
Date: December 7, 1960
Creator: Scott, C. D. & Suddath, J. C.
Partner: UNT Libraries Government Documents Department
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Synthesis of Dimethyl Selenide

Description: The preparation of essentially pure dimethyl selenide for the Isotype Separations Group, Chemistry Division, is described. The compound was prepared by warming a mixture of selenium, sodium hydroxide, sodium formaldehyde sulfoxylate in aqueous solution for several hours at 50°C and then adding methyl iodide. Dimethyl selenide was removed by distillation.
Date: October 7, 1960
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Study of Dispersant Agents for Thorium Oxide

Description: A preliminary study of dispersing agents for thorium oxide has been completed and several of the dispersants have possible uses. Also many of the industrial dispersing agents tested are not usable with thorium oxide due to induced behavior causing balling and caking. The effects of nitric acid concentration have been observed to also effect each dispersing agent.
Date: August 7, 1959
Creator: Bate, L. C. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Radiators for Space Power Plants

Description: An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the… more
Date: August 7, 1959
Creator: Fraas, A. P.
Partner: UNT Libraries Government Documents Department
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A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man

Description: In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.
Date: August 7, 1959
Creator: Sanders, Fred W.
Partner: UNT Libraries Government Documents Department
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Metallographic Examination of ORNL #1, SHE #2

Description: Small Heat Exchanger ORNL #1, type SHE #2, was removed form test stand B after 2071 hours of operation. Thirty-five samples were removed form the entire heat exchanger. The corrosion found on the outside of the tubes exposed to the fluoride mixture ranged to a maximum depth of .004 inches; however, the frequency of occurrence along the tube wall was heavier at the NaK outlet header, which was the hottest area in the heat exchanger. The depth of attack observed on the fluoride side of this heat … more
Date: February 7, 1957
Creator: VanCleve, J. E.; DeVan, J. H. & Crouse, R. S.
Partner: UNT Libraries Government Documents Department
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Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements

Description: One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat com… more
Date: February 7, 1957
Creator: Erwin, J. H. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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Operation of In-Pile Loop L-4-12

Description: Loop L-4-12 was the seventh corrosion test loop operated in HB-4 beam hole at the LITR. The loop was inserted on January 24, 1956, and removed on April 17, 1956. This loop had a titanium core which was attached to the 347 stainless steel loop with special titanium to stainless steel couplings.
Date: January 7, 1957
Creator: Walter, F. J.
Partner: UNT Libraries Government Documents Department
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The Fast Effect in a Beryllium Moderated Reactor

Description: The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.
Date: December 7, 1959
Creator: Novak, P. E.
Partner: UNT Libraries Government Documents Department
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Amendment No. 2 To License Application For Nuclear Test Reactor

Description: GE is amending its application of 6/5/57 to construct and operate the Nuclear Test Reactor in order to incorporate changes in procedure and equipment.
Date: October 7, 1958
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report

Description: This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date: September 7, 1955
Creator: Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
Partner: UNT Libraries Government Documents Department
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The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Description: Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after ir… more
Date: September 7, 1955
Creator: Carrell, R. M.
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys

Description: The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed … more
Date: November 7, 1956
Creator: Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
Partner: UNT Libraries Government Documents Department
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The Oak Ridge National Laboratory Research Reactor Safeguard Report

Description: This memorandum sets forth a recommended uniform basis for designing the ORN shield.This includes design values for power level and emergent radiation, standards values for various material properties, and basic radiation intensities.
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J.P.
Partner: UNT Libraries Government Documents Department
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The Oak Ridge National Laboratory Research Reactor Safeguard Report

Description: The proposed ORNL Research Reactor is designed to serve as a general purpose research tool delivering a maximum thermal flux of 8x10^13 n/cm2-sec at the initial power level of five megawatts. Operation at power levels up to ten megawatts is proposed for such items as sufficient cooling capacity is available to handle the increased heat load. The reactor will use MTR-type fuel elements and beryllium reflector pieces in a 7 x 9 grid with moderation and cooling provided by forced circulation of de… more
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J. P.
Partner: UNT Libraries Government Documents Department
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Remarks on the Double Dispersion Approach to the Bethe-Salpeter Equation

Description: The following remarks are made on the applicability of the double dispersion approach to the Beth-Salpeter equation introduced previously. 1) Any invariant solution of the Bethe-Salpeter equation in ladder approximation satisfies the double dispersion representation when the total energy-momentum is space-lake. 2) There are some exceptional invariant solutions which are not given by the previous method in the equal-mass case, but the existence of such solutions is very unlikely in the unequal-m… more
Date: August 7, 1962
Creator: Nakanishi, Noboru
Partner: UNT Libraries Government Documents Department
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Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor.

Description: Continued operation of F reactor with high water collection rates during the past 12 years has resulted in numerous detrimental effects. In addition to promoting external corrosion tube leaks, water leaks have corroded the Gunbarrel to the biological shield donut assemblies and cast iron thermal shield blocks, thus preventing the majority of tubes in F reactor from unrestrained thermal expansion. Fatigue of the Van Stone flange under the resulting compression loads leads to eventual failure in … more
Date: June 7, 1960
Creator: Russell, A.
Partner: UNT Libraries Government Documents Department
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