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Strain Fatigue Behavior of Zircaloy 2 and 3 at Room Temperature and 550°F

Description: Report describing a study performing strain-fatigue tests performed at room temperature and 550 degrees Fahrenheit on 1/2-inch hot-rolled and annealed plate of Zircaloy 2 and 3. The data is to be used on a S3G unit cell fuel element assembly. The report describes material and test procedure, a presentation of the results, and discussion of the results.
Date: November 18, 1957
Creator: Mehan, R. L.; Groleau, D. T.; Reed, J. H. & Sokol, G. J.
Partner: UNT Libraries Government Documents Department
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Compatibility of Materials in Liquid Metal

Description: Report describing a series of boundary laboratory tests conducted in liquid metal initiated to determine the materials which are best suited for use as sodium- or NaK-lubricated bearings under conditions of boundary lubrication. Results are presented in graphical and narrative form along with a discussion of the testing procedure, equipment, materials, and heat treatment specifications.
Date: August 18, 1951
Creator: Vail, Donald B.
Partner: UNT Libraries Government Documents Department
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Laboratory Studies on Subgrade and Embankment Soils for the Main Canal and Laterals, Hammond Project, New Mexico

Description: Report presenting the results of laboratory tests performed on samples representative of the subgrade and embankment materials proposed for the Main Canal, Gravity Extension lateral, East High Line Lateral, and West High Line Lateral Test were performed to identify the materials and determine their compaction and permeability properties. Test results are summarized in graphical and narrative form.
Date: February 18, 1958
Creator: Ellis, Willard
Location: See Bounding Coordinates
Partner: UNT Libraries Government Documents Department
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Laboratory Tests on Proposed Embankment and Subgrade Materials, Hanover Main Canal No. 2, Hanover Bluff Unit, Missouri River Basin Project

Description: Report discussing laboratory tests performed on samples representing embankment and subgrade materials for Hanover Main Canal No. 2, Hanover Bluff Unit, Missouri River Basin Project (p. 1). Discussion of the results includes analysis of gradation and Atterberg limits, permeability, and erosion resistance with respect to samples collected for the study.
Date: May 18, 1955
Creator: Ellis, W.
Partner: UNT Libraries Government Documents Department
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Power Reactor Development Company Monthly Report: October 1957

Description: Monthly report describing activities and progress related to research and development of Atomic Power Development Associates, Inc.
Date: December 18, 1957
Creator: Power Reactor Development Company
Partner: UNT Libraries Government Documents Department
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Thermal Neutron Fluxes in HRE-2 Determined From Zircaloy-2 Induced ActivityMeasurements, Runs 16 and 17

Description: Thermal neutron fluxes prevailing near some Zircaloy-2 specimens exposed during HRT run 17, and near others exposed during runs 17, 16, 14 and 13 have been determined from measurements of the induced activity in the specimens. The neutron fluxes were calculated for an average core power level of 2 Mv.
Date: December 18, 1959
Creator: Baker, J. E.; Jenks, G. H. (Glenn Herbert), 1916- & Olsen, A. R.
Partner: UNT Libraries Government Documents Department
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Design and Development of Tools to Cut Loose The Diffuser Screens And Resize The Access Flange in The HRT Core Vessel

Description: To repair the core of the HRT a number of tools were developed. This report describes the development of tools for cutting the diffuser screens from the core wall and for resizing the opening in the core access flange. Included are detailed operational procedure for each tool.
Date: November 18, 1959
Creator: Blumberg, R.
Partner: UNT Libraries Government Documents Department
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Consolidated MCF-114 Oil Diffusion Pump

Description: The MCF-1400 is a ten inch, four-stage fractioning pump having an enlarged boiler compartment and external heaters. The first part of this report covers measurements and observations made on the MCF-1400 pump as originally supplied. In the second part certain modifications that have been made on the pump are described, and the effect of these modifications on the performance of the pump are presented.
Date: November 18, 1959
Creator: Normand, C. E.
Partner: UNT Libraries Government Documents Department
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The Fast Fission Factor

Description: The fast fission factor here is described as "the number of neutrons slowing down past the fission threshold of uranium-238 per primary fission neutron, that is, per neutron produced by thermal fission." This definition has been used in the theoretical and experimental formulation of the problem.
Date: September 18, 1959
Creator: Hoke, G. R.
Partner: UNT Libraries Government Documents Department
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Phase Stability of Homogenous Reactor Hot Fuel Solutions

Description: Portions of two samples of HRT fuel solutions were sealed in silica capillary tubes approximately three weeks after they were removed from the reactor and the temperature at which each solution separated into two liquid layers was determined.This report gives the results of these observations.
Date: August 18, 1959
Creator: Barton, C. J.; Gill, J. S.; Hebert, G. M.; Marshall, W. L. & Moore, R. E.
Partner: UNT Libraries Government Documents Department
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Test Results

Description: "The determination of the changes in radiation level in the hairpin loops resulting from continued operation of the reactor at power were studied. The results indicate that the radiation level in the hairpin loop resulting from continued operation of the reactor at power decays to a relatively low level approximately 20 minutes after isolation of the loop."
Date: December 18, 1958
Creator: Duquesne Light Company
Partner: UNT Libraries Government Documents Department
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Test Results

Description: "The purpose of this test is to determine that the system operating pressure is sufficient to meet system design requirements and also to check if leakage occurs through the hydraulic pilot valves. All main hydraulic stop valves operated within the prescribed time limits. Leakage from the system could not be determined because of the unavailability of a proper range test gage at the time the test was performed. The alignment check of the three-way selector valves was not performed because of in… more
Date: December 18, 1958
Creator: Duquesne Light Company
Partner: UNT Libraries Government Documents Department
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The Determination of Trace Elements by Neutron Radioactivation Analysis

Description: Nuclear science has created a new analytical procedure for the determination of trace quantities of many elements. This procedure, called "radioactivation analysis," is a method in which nuclear reactions in a chain-reacting pile (or an accelerator) produce an artificially radioactive isotope of the element being determined. This radioisotope has its own characteristic radiations and mode of decay. Activation analysis is unique because (1) it has great sensitivity of detection for most elements… more
Date: December 18, 1952
Creator: Leddicotte, G. W. & Reynolds, S. A.
Partner: UNT Libraries Government Documents Department
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Some Calculations for the Boiling Reactor Shield

Description: The shield for the boiling reactor experiment is intended to serve for a series of homogeneous reactors. With this in mind the layout shown has been designed to provide flexibility. In order to obtain information on required shield thicknesses some calculations have been made for the first two proposed reactors, the Teapot and a six foot boiling reactor. Calculations include the radiation from the reactor compartment into the instrument room and through the top shield during operation. In the c… more
Date: December 18, 1951
Creator: Aven, R. E.; Eckels, A. R. & Heubenreich, P. N.
Partner: UNT Libraries Government Documents Department
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Design Data for ISHR (Second Edition)

Description: The following design data sheets are for the main circulating system for the ISBR. The data presented are for an intermediate scale, two region, homogeneous converter for production of U233. The data is based on an overall gross power rating of 60MW. These sheets will be supplemented and corrected as more information becomes available. It is requested that recipients of this memo examine the data with which they are concerned and report inaccuracies so corrections can be made in subsequent edit… more
Date: November 18, 1952
Creator: Zapp, F. C. & Haubenreich, P. N.
Partner: UNT Libraries Government Documents Department
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Preliminary Design of Screens for the Inlet of the ISHR Core

Description: In order to produce slug flow in a sphere smooth fluid expansion must be provided from the inlet pipe. This may be accomplished by the installation of diffuser screens. Equations are shown for determining the position and pressure distribution for such screens.
Date: October 18, 1952
Creator: Spiewak, Irving.
Partner: UNT Libraries Government Documents Department
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An Experimental Comparison of the Higgins Continuous Ion Exchanger with a Conventional Fixed-Bed Ion Exchange Column

Description: Under conditions of equal flow rates, flow ratios, and resin bed sizes a laboratory scale hand operated model of a continuous countercurrent ion exchanger invented by IR Higgins gave better results than a conventional fixed ion exchange column in typical recovery concentration separation processes.
Date: June 18, 1952
Creator: Roberts, J. T.
Partner: UNT Libraries Government Documents Department
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Core I Control Rod Drive Mechanisms Periodic Tests. Section I. Ninth Performance. Test Results DL-S-148-I, T-550011

Description: The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.
Date: November 18, 1959
Creator: Pazuchanics, Nicholas
Partner: UNT Libraries Government Documents Department
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Control Air Conditions at the Reactor Chamber. Section I. Test Results DL-S-269

Description: The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air i… more
Date: November 18, 1959
Creator: Eckenrode, Gerald E.
Partner: UNT Libraries Government Documents Department
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Station Radiation Level Survey. Section II. Fifth Performance. Core I, Seed 1. Test Results DL-S-157

Description: The purpose of the test was to determine the level of the radiation field in the Turbine Plant during a significant power run. The initial power level survey had an average radiation level of 0.02 mr/hr. this survey showed and average radiation level of 0.03, which was considered background level. this radiation level was far below the maximum allowable level of 2 mr/hyr. No Neutrons were detected.
Date: November 18, 1959
Creator: McTish, James M.
Partner: UNT Libraries Government Documents Department
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Measurements of Coefficients of Reactivity. Section I. Seventh Performance. 3032-EFPH. Core I, Seed 1. Test Results DL-S-151 (T-550132)

Description: The purpose of the test was to determine the temperature and pressure coefficients of reactivity at zero power. Data was obtained during this test which indicates a new temperature coefficient and a pressure coefficient corrected to station operating conditions of 500 F and 1785 PSIG.
Date: November 18, 1959
Partner: UNT Libraries Government Documents Department
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Liquid Metal Level Instrument

Description: Theory of operation and test results are given for a resistance type of liquid metal level instrument. The voltage across a steel rod in the tank is amplified by a magnetic amplifier and indicated by a milliammeter. Temperature compensation is provided for tank temperatures up to 1000 F.
Date: March 18, 1952
Creator: Robinson, H.; Dows, L. H. & Droms, C. R.
Partner: UNT Libraries Government Documents Department
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Effect of Core Corrosion Sample Assembly on HRT Critical Concentration

Description: An estimate has been made of the critical fuel concentration in the HRT, taking into account the effect of the core corrosion sample assembly. The estimate is based on a number of previous calculations of critical concentration in an un-poisoned reactor and one calculation of critical concentration as a function of poison level. The makeup of the first core corrosion sample assembly was used in calculating equivalent neutron poisoning effects. Figure 1 shows the estimated critical concentration… more
Date: July 18, 1957
Creator: Haubenreich, Paul N.
Partner: UNT Libraries Government Documents Department
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Trip to Selas Corporation of America

Description: On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date: June 18, 1957
Creator: Franco-Ferreira, E. A.
Partner: UNT Libraries Government Documents Department
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