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Hazards Report for the SM-1 Core II Without Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core … more
Date: April 19, 1961
Creator: Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
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Review of the Corrosion Product Radioactivity Program at the Army Package Power Reactor : Alco R & D report

Description: Abstract: An analysis and a summary are.given of the radioactivity buildup program at the Army Package Power Reactor during the last nine months. · Due to the wide fluctuation of water and crud results, only general interpretations can be made with this data. Metal test coupon data indicate a substantially greater buildup on Croloy 16-1 metal than on Type 304 stainless steel. Coupled with the decreased ability to remove the radioactivity buildup on Croloy 16-1 by conventional descaling techniq… more
Date: April 25, 1958
Creator: Medin, A. L.
Partner: UNT Libraries Government Documents Department
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Theory of Asymmetric Arrays of Control Rods in Nuclear Reactors

Description: Introduction: Seldom does the actual arrangement of control elements in a nuclear reactor confers to the ideal and convenient mathematical array. In order to achieve shim control. safety and regulation, it is desirable to design with rods of different sizes and materials. With given fuel element arrangement, typically in square or hexagonal lattice spacing, there will be rods located at different distances form the center of the core and from each other. As the reactor operates, absorbers wil… more
Date: April 25, 1959
Creator: Murray, Raymond L.
Partner: UNT Libraries Government Documents Department
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DuPont Prototype Safety and Control Rod Drive Testing

Description: Summary: Prototype testing of the safety and control rod drives indicated that both units functioned properly. No major problems were encountered during testing. Seal leakage data collected indicated that the seal units were performing satisfactorily. Scram times during both cold and hot testing were excellent and actually better than expected.
Date: April 25, 1960
Creator: VandeMark, G. M. & Krause, P. S.
Partner: UNT Libraries Government Documents Department
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A Survey of the Effects of Neutron Irradiation on the Impact and Other Mechanical Properties of Pressure Vessel Steels for the SM-2 Reactor

Description: Abstract: This technical report summarizes the data obtained in a recent literature survey conducted to determine the effects of neutron irradiation on the impact and other mechanical properties of both ferritic steels and austenitic stainless steels. The survey was primarily aimed at obtaining sufficient data on the behavior of pressure vessel steels at high integrated neutron flux levels in order that a reference material of construction could be selected for the SM-2 (APPR-1B) reactor vesse… more
Date: April 1, 1960
Creator: Kelleman, Richard William.
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility Studies Progress Report: April 1965

Description: From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date: April 1965
Creator: Astley, E. R.
Partner: UNT Libraries Government Documents Department
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Runaway Analysis for a Gas Cooled Reactor

Description: From abstract: "This report presents an IBM digital computer program that solves numerically and simultaneously the equations that describe gross reactor behavior under runaway conditions."
Date: April 1961
Creator: Becker, Richard A.
Partner: UNT Libraries Government Documents Department
open access

Floating-Decimal Matrix Inversion

Description: Use of Crout Method in floating-decimal notation in IBM Model I Card-Programmed Calculator.
Date: April 1955
Creator: Trantham, F. M., Jr.
Partner: UNT Libraries Government Documents Department
open access

A Versatile Spectrometer Magnet Power Supply

Description: Early results from actual laboratory operation of a more versatile magnet supply.
Date: April 15, 1963
Creator: Groppe, W. A.
Partner: UNT Libraries Government Documents Department
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The Design and Performance of Levitation Melting Coils

Description: The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.
Date: April 26, 1963
Creator: Hulsey, William Jewell
Partner: UNT Libraries Government Documents Department
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A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
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Television System Study for Accident Recovery : Phase I

Description: From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."
Date: April 1966
Creator: Talpis, N. A. & Burge, D. L.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the Battelle Research Reactor

Description: From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
Date: April 4, 1955
Creator: Chastain, J. W.; Redmond, R. F.; Klickman, A.; Anno, J. & Fawcett, S. L.
Partner: UNT Libraries Government Documents Department
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Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices

Description: From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."
Date: April 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
Partner: UNT Libraries Government Documents Department
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