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12" Sodium Flow Controller. Permanent Magnet Coupling. Magnetic Calculation Manufacture and Test Results

Description: In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)
Date: August 18, 1961
Creator: Flator, H. E.
Partner: UNT Libraries Government Documents Department
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40-tube overbore facility location, C Reactor

Description: Possible locations of the projected 40-tube overbore facility at the C Reactor are discussed from the standpoint of obtaining conversion ratio data applicable to a full-reactor overbore program.
Date: April 19, 1961
Creator: Nilson, R.: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reac… more
Date: February 20, 1961
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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105-C overboring thirteen tube outage, March 6, 1961--March 10, 1961

Description: C Reactor was shut down on a scheduled basis at 8:30 a.m. March 6, 1961 for the purpose of overboring 17 process channels. this report will cover that outage and discuss problems encountered in completing the tasks involved in overboring.
Date: March 24, 1961
Creator: Munro, C. A.
Partner: UNT Libraries Government Documents Department
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1A Heat Exchanger Leak Test. Core I, Seed 2. Test Evaluation. Section 2

Description: An investigation was conducted to determine which tubes of the 1A loop heat exchanger are leaking. Air pressure and probing tests are inconclusive and cannot be used to verify chemical sampling. (J.R.D.)
Date: July 24, 1961
Partner: UNT Libraries Government Documents Department
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1B HEAT EXCHANGER LEAK TEST. CORE I, SEED 1. Test Results

Description: Descriptions are given of various procedures used in determining leaks in the tubes of the 1B heat exchanger. Air pressurization tests determined leakage and leak rate of nine tubes. The leak-location-detector-probe method was found promising for locating defects along the length of the tube. Results of the probalog, dye-penetrant, and ultrasonic tests proved inconclusive in determining leak locations. (B.O.G.)
Date: February 24, 1961
Partner: UNT Libraries Government Documents Department
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2000 KILOWATT SODIUM TEST FACILITY. Project Description and Progress Reports, June 30, 1958 through September 30, 1959

Description: The design and construction work completed on the 2000-kw Sodium Teat Facility during the period from April 1958 to Oct. 1959 is described. The purpose of the facility project in to test models of equipment components which are to be used in a moltsn plutonium, sodiumcooled fast reactor. (D. L.C.)
Date: March 1, 1961
Creator: Whinery, L.A.
Partner: UNT Libraries Government Documents Department
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The A.A.E.C. Atmospheric Pressure Heat Transfer Rigs

Description: This technical report describes two atmospheric pressure rigs with associated equipment designed for investigating heat transfer and friction characteristics of different type of "roughened" surfaces to develop suitable surfaces for an H.T.G.C.R. fuel element. Operating details are given together with techniques used to measure heat transfer and friction on a surface assembly incorporating selected "roughened" surfaces. Methods for calculating Stanton numbers, friction factors, and Reynolds num… more
Date: 1961
Creator: Lawther, K. R. & Draycott, A.
Partner: UNT Libraries Government Documents Department
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Acceptor Dopants for Lead Telluride

Description: Alternative P-type dopants such as, Th, P, and As were studied. Ingots were grown from a melt containing one at.% dopant and their electrical properties evaluated. Also, sintered pellets of PbTe were doped by exposure at high temperature to gaseous dopants. In most cases, the doping concentrations obtained were insufficient for SNAP 10A requirements. In the case of As, however, doping of Te-rich PbTe, the desired heavy doping was obtained. These preliminary studies suggest that dopants other th… more
Date: December 1961
Creator: McCaldin, J. O.
Partner: UNT Libraries Government Documents Department
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Activity Build-Up Control by High pH Coolant. A Literature Survey

Description: A survey was made of unclassified literature dealing with the control of activity build-up in pressurized water reactors by high-pH coolants. Survey results indicate that a high-pH coolant is desirable for control of induced radioactivity build-up in pressurized water reactors containing significant amounts of stainless steel and that no significant hazards are introduced by adoption of a high-pH coolant. Lithium hydroxide was found to be the most acceptable agent for coolant pH control. Strong… more
Date: January 23, 1961
Creator: Bergen, C. R.
Partner: UNT Libraries Government Documents Department
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An Adiabatic Motion Of Charged Particles In Electromagnetic Fields

Description: The guiding center motion and the adiabatic invariants of charged particle trajectories in electromagnetic fields are treated in this review. General and specific theories of charged particle motion are also reviewed.
Date: January 1961
Creator: Northrop, Theodore G.
Partner: UNT Libraries Government Documents Department
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Adsorption of Krypton and Xenon by Various Materials

Description: The adsorptive capacities of various inorganic adsorbents and activated charcoals for krypton and xenon were determined. Columbia-G activated charcoal had the highest capacity for both krypton and xenon at pressures from 0.01 to 125 mm Hg and temperaturens from 2 to 85 deg C. If a value of 1 is assigned to the capacity of this charcoal at 28 deg C for krypton, other charcoals range from 0.63 to 0.84, molecular sieves (except 4A) from 0.11 to 0.20, and some silica genls from 0.05 to 0.07. Variou… more
Date: December 1, 1961
Creator: Lloyd, M. H. & McNees, R. A.
Partner: UNT Libraries Government Documents Department
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Advanced Engineering Preliminary Program Planning, Rough Draft

Description: The purpose of this document is to assembly certain job elements which may become part of the Advanced Engineerng Subsection programs, so that those individuals who may be requested to participate in such programs may be aware of the nature and form of Advanced Engineering planning.
Date: April 20, 1961
Creator: Towle, H.C.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Aerial Radiological Monitoring System: Part 2. Performance, Calibration, and Operational Check-Out of the EG&G ARMS-II Revised System

Description: Report describing "the design, installation, and performance of the Edgerton, Germeshausen & Grier, Inc., Aerial Radiological Monitoring System used in Phase II of the Aerial Radiological Monitoring Survey (ARMS-II)" (p. 5). Contains descriptions and photographs of its components and descriptions of test runs.
Date: October 1961
Creator: Hand, J. E.; Guillou, R. B. & Borella, H. M.
Partner: UNT Libraries Government Documents Department
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Aerial Radiological Monitoring System: Part 3. Electronic Processing of ARMS-II Data

Description: Report detailing the instrumentation and system performance of the Aerial Radiological Monitoring Survey (ARMS-II), a system used "to perform aerial surveys of ground radioactivity. It supplies both geographical position and radioactivity data in digital form, suitable for use with automatic plotting procedures" (p. 5)
Date: October 1961
Creator: Hand, J. E. & Borella, H. M.
Partner: UNT Libraries Government Documents Department
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