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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV

Description: Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nuclear evaluation, thermal and hydraulic analysis, description of tests to be performed, and discussion of containment integrity and maximum accident considerations.
Date: March 30, 1961
Creator: Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
Partner: UNT Libraries Government Documents Department
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Nuclear Port Survey of the State of New York

Description: Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.
Date: November 1961
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Description: Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
Partner: UNT Libraries Government Documents Department
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Progress Report Pebble Bed Reactor Program: June 1, 1959-October 31, 1960

Description: From abstract: This report describes analytical and development work in connection with the Pebble Bed Reactor concept. The principle involved in the reactor is the heating of graphite pebbles by the fission of contained uranium and transfer of the heat generated to helium which is circulated through the permeable bed.
Date: July 1961
Partner: UNT Libraries Government Documents Department
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Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor

Description: From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.
Date: November 15, 1961
Creator: Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Partner: UNT Libraries Government Documents Department
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Reactor Containment Design Study

Description: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date: May 18, 1961
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department
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Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator

Description: Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.
Date: October 19, 1961
Creator: Allen, Charles F.
Partner: UNT Libraries Government Documents Department
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The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)

Description: "An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date: July 30, 1961
Creator: Gehman, William G.
Partner: UNT Libraries Government Documents Department
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Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator

Description: Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date: February 28, 1961
Creator: Webster, L. J.
Partner: UNT Libraries Government Documents Department
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Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Metallurgical Aspects of SRE Fuel Element Damage Episode

Description: Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
Partner: UNT Libraries Government Documents Department
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Investigations of Neutron Penetration in TiH and Steel Slabs

Description: Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date: May 15, 1961
Creator: Karcher, R. H.
Partner: UNT Libraries Government Documents Department
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Corrosion and Activity Transfer in the SRE Primary Sodium System

Description: Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date: October 30, 1961
Creator: Johnson, H. E.
Partner: UNT Libraries Government Documents Department
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Critical Path Scheduling in Maintenance

Description: Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Partner: UNT Libraries Government Documents Department
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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
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 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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