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Properties of High-Temperature Ceramics and Cermets: Elasticity and Density at Room Temperature

Description: From Introduction: "The present paper contains detailed descriptions of the methods used in calculating both the elastic constants and the statistical parameters. These detailed descriptions have been included for two reasons: (1) To leave no doubt as to the exact procedure, and (2) to act as a guide to other workers who might wish to make similar determinations."
Date: March 1, 1960
Creator: Lang, S. M.
Partner: UNT Libraries Government Documents Department
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Conductive Flooring for Hospital Operating Rooms

Description: Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.
Date: March 21, 1960
Creator: Boone, Thomas H.; Hermach, Francis L.; MacArthur, Edgar H. & McAuliff, Rita C.
Partner: UNT Libraries Government Documents Department
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Proposal for an Advanced Engineering Test Reactor : ETR II

Description: Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date: March 17, 1960
Creator: deBoisblanc, D. R.
Partner: UNT Libraries Government Documents Department
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Halogen Collector Test Program

Description: Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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Fast Reactor Core Design Parameter Study

Description: Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
Partner: UNT Libraries Government Documents Department
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Enrico Fermi Atomic Power Plant

Description: Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.
Date: March 1960
Creator: Atomic Power Development Associates
Partner: UNT Libraries Government Documents Department
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Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Description: Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date: March 15, 1960
Creator: Millhollen, M. K.
Partner: UNT Libraries Government Documents Department
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Heavy-Water-Moderated Power Reactors: a Status Report

Description: From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."
Date: March 1960
Creator: Babcock, Dale Friend
Partner: UNT Libraries Government Documents Department
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Qualification Approval Tests on resistance products Co.`s type {open_quotes}H{close_quotes} Carbon Composition resistors (0.2 and 40 Megohm)

Description: Engineering Work Requests ESE-48 & 49 established a program for performance of Qualification Approval Tests on RPC`s 0.2 and 40 meghom Carbon Composition Resistors. This report is an accounting of these tests wherein (50) samples of each component were subjected to QA tests per drawings 8O2C250 and 802C251. Tests are explained and results tabulated.
Date: March 25, 1960
Creator: Dixon, L.W.
Partner: UNT Libraries Government Documents Department
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Cathode brazing control for GEXF

Description: As a result of repeated epidemic losses of brazed cathodes at GEXF, the engineering work necessary to determine the best brazing cycle and the controls necessary to insure reproducibility and high yields in the future was carried out by means of EN-297. Included are the procedures used and the tests made to verify the conclusions drawn and the recommendations made.
Date: March 8, 1960
Creator: Thinnes, E.L.
Partner: UNT Libraries Government Documents Department
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Graphite burnout, interim report on IP-25-A (PT-105-532-E)

Description: Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of carbon. In the case of CO{sub 2}-graphite interaction, the reaction rate is not significant until about 550 C. Water oxidizes graphite, very roughly, three times faster than CO{sub 2}. Air will oxidize graphite appreciably at temperatures below 500 C. Graphite removal from Hanford reactors is very important, since graphite is used both as a structural support and a moderator for neutrons. Griggs has shown that small graphite samples oxidized to 10 per cent weight loss had only about one-half their original compression strength. Hence, the longevity of the reactors depends to a great extent on maintaining a low graphite oxidation rate. A means of monitoring the extent of graphite loss, i. e., the burnout rate, is necessary to establish future reactor operational standards. Presently, weighed samples of reactor grade graphite are placed along the length of an empty process channel in each reactor. Thus, a sample is exposed to the reactor`s ambient conditions of power level, moderator temperature, and gas composition. This program was initiated in the vicinity of June, 1953 by Woodley. This report presents data on graphite burnout obtained from in-reactor experiments authorized under IP-25-A (PT-105-532-E) from August, 1957 to January, 1960. Burnout rates are obtained by a direct measurement of the weight loss of control graphite samples exposed to the reactor atmosphere.
Date: March 15, 1960
Creator: Ryan, B. A. & de Halas, D. R.
Partner: UNT Libraries Government Documents Department
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LRL background measurements program for ICBM discrimination

Description: Several proposals have been made for discriminating between Intercontinental Ballistic Missiles (ICBM) and decoys. Primary fundamental particles or high energy electromagnetic radiation can be scattered from or can activate the targets. The secondary radiation is observed by directional detectors that are positioned close-by and the information is transmitted to control centers on the ground. Lawrence Livermore Laboratory proposes a program for measurements of the natural space radiations. Eventually, the space backgrounds must be measured before a satisfactory discrimination system can be perfected. Past and scheduled background measurements are described and a measurement program is proposed.
Date: March 9, 1960
Partner: UNT Libraries Government Documents Department
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PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959

Description: From abstract: The principal efforts are the furthering of the final design and preparation of specifications for some long-lead components. The entire power plant has been divided, for final design purposes, into 37 subsystems. The status of work on each subsystem at the close of the period is reported.
Date: March 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Strontium 90 Power Project: Final Summary Report

Description: From summary: The primary purpose of this project is to determine the feasibility of converting reactor waste Strontium-90 into a safe and useful source of electrical energy. Secondary purpose is physical and environmental testing of the power conversion device or thermoelectric couples. This required actual fabrication of a 100-thermal-watt strontium titanate fuel element
Date: March 1960
Partner: UNT Libraries Government Documents Department
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Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling Tests of Porous Uranium

Description: Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date: March 15, 1960
Creator: Wilkinson, L. E.
Partner: UNT Libraries Government Documents Department
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Automatic Recording Unit

Description: From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date: March 29, 1960
Creator: Ross, Frank A.
Partner: UNT Libraries Government Documents Department
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Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: January-March 1960

Description: Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: March 31, 1960
Partner: UNT Libraries Government Documents Department
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An Experimental Gamma Irradiator for Hospital Sterilization

Description: From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date: March 7, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
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20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962

Description: From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
Date: March 1960
Creator: Vortman, Luke J. & MacDougall, H. R.
Partner: UNT Libraries Government Documents Department
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