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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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Shielding on 30-Inch Pipe

Description: The materials of construction and the design of the shielding for a 30 inch pipe are presented. A calcium borate material and a borated diatomaceous earth-luminate concrete equally satisfactorily and both are considered for the shielding of the pipe.
Date: February 5, 1958
Creator: Morabito, John J.
Partner: UNT Libraries Government Documents Department
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Basic Concept of the Inert Gas System for Primary Sodium

Description: The design values which were selected and the reasons for selecting them are given for the Fermi Reactor inert gas system. The concept of the system which is to be used to prepare the detailed flow sheet and to design the system components is described. The gas is to be either helium, argon, or nitrogen.
Date: February 3, 1958
Creator: Kendall, W. W. & Chase, W. L.
Partner: UNT Libraries Government Documents Department
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Mass Transfer by High Temperature Liquid Sodium. Interim Progress Report 1

Description: The general objective of the program is to increase existing knowledge on the behavior of solid metals in liquid metal environments. Higher temperatures, longer operating life, and increase reliability of liquid metal cooled reactors is the ultimate goal. The initial phase of the program is concerned primarily with an experimental investigation of corrosion and mass transfer by sodium in dynamic, monometallic polythermal systems, at temperatures in the range from 1000 - 1600 F. Research in diff… more
Date: February 3, 1958
Creator: Holman, W. R. (William Reid), 1918-
Partner: UNT Libraries Government Documents Department
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Prescoping Optimization for Selection of Enriched Uranium Gas-Cooled Power Reactor Design

Description: A preliminary set of performance calculations were made for enriched reactor cores based on five cylindrical vessel designs ranging from13 to 36 feet in diameter. The capital costs per kilowatt of electrical plant output as shown in Table II indicate than an economic optimum selection of pressure vessel size should be either the 25 foot or the 36 foot vessel.
Date: February 14, 1958
Creator: Farmer, W.; Hill, E.; Lang, P.; Trickett, K. & Matovich, S.
Partner: UNT Libraries Government Documents Department
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New Developments in the Theory of Pressure Broadening

Description: An investigation was made into various branches of the theory of pressure broadening by solving two problems: that of treating the motion of the perturbers quantum mechanically and that of overlapping lines. Both problems are solved only in the impact approximation, but this is adequate when the perturbers are electrons, which is the practical case. In addition, the validity conditions of this approximation are examined. (auth)
Date: February 19, 1958
Creator: Baranger, Michel
Partner: UNT Libraries Government Documents Department
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Zirconium Hazards Research

Description: "The study of the sensitivity characteristics of Zr samples such as sponge, scrap, foil, and powder was continued. Of particular interest was the determination of the relative sensitivity of these materials to such stimuli as electrostatic discharge and an induced shock wave. The investigation of the zirconium-water reaction and zirconium-gas reactions at relatively low temperatures was continued."
Date: February 28, 1958
Creator: Herickes, J. A.; Richardson, P. A.; Weiss, M. & Geuerbterm, G.
Partner: UNT Libraries Government Documents Department
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Water Hammer Tests Loop Able Pwp Land Reactor, 1957

Description: "This report essentially substantiates the preliminary data reported ln WAPD-PWR-PMF-898. The Primary Coolant System of the Pressurized Water Reactor (PWR) at Shippingport, Pennsylvania, comprises four loops. Each of the loops has one pump to control the mass rate of water flow-. A series of tests were conducted on the cooling system of the PWR land reactor to determine the magnitude and duration of the water hammer pressure wave resulting from check valve closure. The water hammer pressure wav… more
Date: February 28, 1958
Creator: Brewer, G. A. & Wing, J. C.
Partner: UNT Libraries Government Documents Department
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Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work

Description: This report is presented in order to provide a satisfactory system of symbols and identifications for process-instrumentation equipment and to promote a uniformity of practice that will simplify and expedite instrumentation work. It is intended that the systems presented here should be capable of designating and identifying the multitude of instrumentation items which are used for control and operation of conventional processes, as well as for specialized work peculiar to ORNL. Instrument Socie… more
Date: February 21, 1958
Creator: Adams, R. K.; Davis, D. G. & Hyland, R. G.
Partner: UNT Libraries Government Documents Department
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Final Summary Safeguards Report For The General Electric Test Reactor

Description: This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.
Date: February 20, 1958
Creator: Andersen, R. K. & Jacobs, I. M.
Partner: UNT Libraries Government Documents Department
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Radiochemical Analysis of Crud from the Army Package Power Reactor

Description: Abstract: A study has been made of the radiochemical composition and the specific activity of insoluble corrosion products (crud) removed from the primary system of the APPR-1. This report presents the results of analysis of twelve crud samples collected during the interval from September 3, 1957 to December 1, 1957. The samples were radiochemically analyzed for long-lived gamma emitting nuclides only. Data are presented on the measured values of the specific activity of crud, the ratios of th… more
Date: February 15, 1958
Creator: Zegger, J. L.; Small, W. J. & Brown, W. S.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation, monthly activities report, January 1958

Description: This document presents a summary of work and progress at the Hanford Engineer Works for January, 1958. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project secti… more
Date: February 15, 1958
Creator: Parker, H. M.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Record Report: January 1958

Description: This document details activities of the irradiation processing department during the month of January, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: February 21, 1958
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Application of a First-Production Evaluation System to Help Assure Material Compatibility and Functional Reliance

Description: The ultimate achievement of a research and development program at Sandia. Corporation, as at any other AFX or DOD project, is the physical design of a component or weapon system of high reliability. The design accomplishment is initially established when the basic drawings and specifications are released for production. These drawings and specifications are often based on engineering evaluations of bread- .board and early so-called & quot;gold plated prototypes. However, the design accomplishme… more
Date: February 1, 1958
Creator: Ballard, Douglas
Partner: UNT Libraries Government Documents Department
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Status report -- Fuel element machining

Description: This report summarizes the design and development work completed since May, 1957; the current status of fuel element matching problems, and the plans for future modifications to improve machining techniques.
Date: February 12, 1958
Creator: Nickolaus, J. W.
Partner: UNT Libraries Government Documents Department
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Increase in reactor power ratings through increased H{sub 2}O and D{sub 2}O flow rates

Description: As a part of the Productivity Increase Program, consideration should be given to further gains in 100 Area production levels which can be achieved by further increases in both light and heavy water flow rates. This memorandum presents a summary of the power level gains which should be achieved from the flow increases under consideration, a discussion of the costs and production losses which might apply, and a brief listing of some other considerations which might influence any decision to incre… more
Date: February 12, 1958
Creator: Holmes, R. C.
Partner: UNT Libraries Government Documents Department
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HAPO irradiation of capsules containing UO{sub 2} specimens

Description: A knowledge of the effect of reactor irradiation on the properties of UO{sub 2} is relevant to the design and evaluation of UO{sub 2} fuel elements for the PRTR. Of particular interest is the effect of reactor irradiation on the thermal conductivity of sintered UO{sub 2} and the type, mechanism, and extent of radiation damage in sintered UO{sub 2}. In the latter case the study of fractured surfaces of irradiated UO{sub 2} specimens is a method of determining the extent of radiation damage. It i… more
Date: February 17, 1958
Creator: Newkirk, H. W.; Millhollen, M. K. & Brite, D. W.
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department monthly report, January 1958

Description: This report describes the operation of the fuels preparation department for the month of January, 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.
Date: February 28, 1958
Partner: UNT Libraries Government Documents Department
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E-metal dissolvers, Redox

Description: In December 1957, the proposal for Project CG-772, ``E-Metal Dissolvers -- Redox`` was returned for reconsideration in order that the units might be designed to accommodate higher enrichment fuels, if practical. Alternate design approaches have been under consideration since that time. It is the purpose of this document to summarize the parameters involved and to present the recommendation developed from the joint thinking of Hanford Laboratories, Research and Engineering, Facilities Engineerin… more
Date: February 19, 1958
Creator: Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department
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Pump-Down Times for the β⁺ Ray and Felix Experiments

Description: "The e-folding time for the free-molecule pump-out time of the vacuum tank used for the β⁺ ray experiment (N¹⁹ at 20°C) is found to be of the order of 46 millisec, and that used for the Felix experiment (D₂ at 20°C) of the order of 12 millisec. In the Felix tank a particle bounces off of the walls on the average about 30 times before escaping, hence a "getter" material coated on the walls of the tube should result in a slightly more rapid pump-out time."
Date: February 4, 1958
Creator: Gibson, Gordon & Newcomb, William A.
Partner: UNT Libraries Government Documents Department
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Analysis of yttrium oxide exchange samples

Description: Report detailing the results of several yttrium oxide analyses. Four different institutions were given 50 grams of yttrium oxide to analyze following the Yttrium Analytical Conference on November 7th and 8th, 1956. This report details the results of those four different institutions.
Date: February 1958
Creator: Rodden, Clement J.
Partner: UNT Libraries Government Documents Department
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