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Control and Dynamics Performance of a Sodium Cooled Reactor Power System

Description: Introduction: Objectives and Method of Approach. High plant efficiencies can be realized without excessively high core temperatures and high coolant pressures by the use of liquid metal coolant. In an attempt to prove the feasibility of liquid sodium as a reactor coolant ALCO Products, Inc., under sponsorship of the Atomic Energy Commission, is undertaking a design study of three vital system components: the intermediate exchanger, the boiler, and the superheater. Since, in the past programs,… more
Date: 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design

Description: This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be encl… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis

Description: Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to mainta… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications

Description: Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance

Description: This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Scale "Up or Down" Analysis for Prototype Test

Description: Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually … more
Date: May 1, 1960
Creator: Alco Products (Firm).
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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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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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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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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SM-1 Research and Development Program: Long-lived Induced Activity Buildup During SM-1 Core I Lifetime. Task XVIII, Phase I

Description: Abstract: The results of activity buildup studies in the SM-1 performed during Core I lifetime (June 3, 1957 to April 28, 1960) are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Radiation levels after reactor shutdown are presented, as well as mathematical equations used to account for the observed activity levels. The data have shown that Co60 is the major contributor to radiation levels in… more
Date: November 30, 1960
Creator: Bergmann, C. A.; Bergen, C.; Cox, J. F.; Chupak, J. & Grant, L. G.
Partner: UNT Libraries Government Documents Department
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Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Description: Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-… more
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Partner: UNT Libraries Government Documents Department
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Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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SM-2 Fuel Element Welding Development : Task 5.0

Description: Abstract: Development of welding processes for stainless steel fuel elements, previously initiated by Alco Products, was continued in Task 5. Three objectives were accomplished; (1) development of a suitable reference welding process, (2) evaluation by out-of-pile tests of the structural integrity of reference welded fuel elements, and (3) preparation of specifications and fabrication procedures for the reference welding process.
Date: August 11, 1960
Creator: Harris, R. L.
Partner: UNT Libraries Government Documents Department
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Transistorized Pulse Counting Equipment

Description: This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date: July 26, 1960
Creator: Henry, John J.
Partner: UNT Libraries Government Documents Department
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Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
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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Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
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The ML-1 Design Report

Description: From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
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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