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Final Safety Analysis Report: SNAP 1A Radioisotope Fueled Themonuclear Generator

Description: The following report is the final safety analysis report for the Task 2 Radioisotope Powered Thermoelectric Generator prepared by The Martin Company. It presents analyses, tests and evaluation of the operational safety criteria for the generator.
Date: June 30, 1960
Creator: Dix, George P.
Partner: UNT Libraries Government Documents Department
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SNAP 7D: stronium-90 fueled thermoelectric generator power source, thirty-watt U.S. Navy Floating Weather Station, final report

Description: The objectives of the SNAP-7D program were to design, manufacture, test and deliver a thirty-watt electric generating system for a modified U.S. Navy NOMAD-class weather buoy to be stationed in the Gulf of Mexico. The sixty-watt Strontium-90 thermoelectric generator, the relay panel, the batteries, and the installation of the system in a boat-type buoy are described. In addition to delivering the power supply, many tests were required for the SNAP-7D system to demonstrate its conformance to the… more
Date: March 15, 1963
Partner: UNT Libraries Government Documents Department
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Snap 7B: Stronium-90 Fueled Thermoelectric Generator Power Source, Thirty- Watt U.S. Coast Guard Automatic Light Station. Final Report

Description: The objectives of the SNAP 7B program were to design, manufacture, test and deliver a thirty-watt electric generating system for a U. S. Coast Guard Automatic Light Station. This report describes the sixty-watt, strontium-90 thermoelectric generator, the converter, the batteries, and the installation of the generator into the container. The electrical tests of the generator and of the system, the shock and vibration tests, and the tests at the environmental temperature extremes are discussed.
Date: June 1963
Partner: UNT Libraries Government Documents Department
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Data Telemetry Package Powered by Strontium-90 Fueled Generator: Final Report

Description: From foreword: This report is divided into two parts: Part A covers the data telemetry package used for the transmission of weather station data, and Part B covers the generator which supplies power to the data telemetry package.
Date: September 1961
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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PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960

Description: From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.
Date: April 5, 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960

Description: From abstract: Reactor development work includes: initiation of the flexible zero-power test (PMZ-1) experimental program, fabrication and delivery of a PM-1 type fuel element, continuation of reactor flow and heat transfer tests, development work on rare earth control rods, and testing and redesign of the prototype magnetic jack-type control rod actuator.
Date: July 5, 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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PM-1 Nuclear Power Plant Program: Final Progress Report, September 1, 1962 Through Completion

Description: From abstract: The principal efforts during the final period were concerned with plant testing, modifications to the plant to enable it to produce full design load at high ambient temperatures, the compilation and evaluation of plant performance data, preparation of documents and transfer of the plant to the AEC and final resolution of all outstanding contract scope items.
Date: July 15, 1963
Partner: UNT Libraries Government Documents Department
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Special Welding Techniques : Final Summary Report

Description: From foreword: This is the final report on Special Welding Techniques. The work of the third and final year is discussed in detail, and the accomplishments of the first two years are summarized.
Date: January 1957
Creator: Mueller, John; Maxwell, William & Siltanen, James
Partner: UNT Libraries Government Documents Department
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Proceedings of the ANPP Reactor Analysis Seminar, October 11 and 12, 1960

Description: From foreword: Seminar to afford personnel associated with work in the field of reactor analysis within the various programs an opportunity to more thoroughly acquaint themselves with current activities and experience throughout the ANPP.
Date: January 1961
Creator: O'Brien, J. F.
Partner: UNT Libraries Government Documents Department
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ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel

Description: From summary: This report describes an experimental study performed on critical arrays of water-moderated, flat plate, laminated fuel bundles. The experiments were performed in support of analytical studies undertaken in the ANPP Code Development Program. The fuel bundles were built up using fully enriched uranium metal foils, stainless steel plates and boron stainless steel plates.
Date: May 1962
Creator: Welshans, L.
Partner: UNT Libraries Government Documents Department
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Development of Iron-Aluminum Base Alloys for Gas Cooled Reactor Components: Second Quarterly Progress Report, June 1958

Description: From summary: Description of a program undertaken to develop an iron-aluminum base alloy for service approaching 1600 degrees Fahrenheit. The program includes development of an alloy, development of techniques for fabricating fuel elements, reprocessing investigations and irradiation testing of iron-aluminum base alloys.
Date: June 1958
Creator: Mueller, J.
Partner: UNT Libraries Government Documents Department
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PM Research and Development Task 1.0 : Core 2 Final Design Report

Description: From summary: This report describes the final design of Core 2, which is being developed primarily as a replacement core for the PM-1 and PM-3A nuclear power plants. In addition, the thermal and hydraulic capabilities were investigated; these indicate applicability of the core to higher powered PM-type plants.
Date: April 1963
Creator: Russo, F.; Brittain, W.; Lightner, R. & Baer, R.
Partner: UNT Libraries Government Documents Department
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SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 7, May 1, 1962-July 31, 1962

Description: From introduction and summary: The effort in this area (Task 8 portion of contract) has been confined to operating the reliability model. There have been fluctuations in output power that can be attributed to variations in the operating parameters, plus an increase in the internal resistance.
Date: 1962
Creator: McDonald, W. A.
Partner: UNT Libraries Government Documents Department
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Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report

Description: From summary: Description of an iron-aluminum-chromium alloy, DB-2, used as the starting point of a program initiated to develop an iron-aluminum base alloy for cladding gas-cooled reactor core components. Secondary aims were to gain knowledge of fuel element fabric-ability, radiation effects and acid solubility of iron-aluminum base alloys.
Date: April 1959
Creator: Tate, Frank
Partner: UNT Libraries Government Documents Department
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Fluidized Bed Reactor Study: Phase I - Feasibility

Description: From abstract: The Fluidized Bed Reactor (FBR) consists of a bed of fuel pellets which circulate in a confined core region as the result of the upward flow of fluid through the particles. In the present concept the fluid acts as a fluidizing, coolant and reactor moderator medium. This report is the results of the Phase I study to determine the feasibility of this concept.
Date: February 1959
Partner: UNT Libraries Government Documents Department
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Feasibility Study of Water-Cooled Thermionic Nuclear Power Plant

Description: From introduction: Feasibility of the thermionic reactor system determined by a comparison of plant features such as component and plant reliability, capital and operating costs, and the number of air-transportable modules required, to existing portable nuclear power plants.
Date: November 1962
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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PM-3A Nuclear Power Plant Program

Description: From summary: Progress report on the production of detailed piping and equipment installation drawings for the PM-3A nuclear power plant program. Attention has been paid to the procurement of those valves and specialty items associated with the piping system.
Date: July 21, 1961
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
open access

ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959

Description: From introduction: The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water cooled and moderated reactors to predict accurately reactivity, rod positions and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: November 1959
Creator: Olsen, T. M.; Welshans, L. & Eicheldinger, C.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A

Description: From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.
Date: February 1962
Creator: Brooks, Phillip M. & Keegan, James J.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Meteorological Station, SNAP-7C

Description: From introduction: The primary objectives in designing a nuclear safe radiostrontium generator are: continuous absolute containment of the radiostrontium fuel, which is a relatively insoluble and chemically stable fuel compound, and biological shielding of the direct radiation from the heat source. This report evaluates the safety aspects of a prototype Strontium-90 fueled generator which will be utilized by the U.S. Navy to power and unattended automatic meterological station.
Date: 1962
Creator: Brooks, Phillip M. & Keegan, James J.
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Re-entry Study High Altitude Burnup: Volume 2

Description: From summary: This report broadly reviews several methods of determining the fate of radioactive fuels (in space power units) burned up on re-entry into the earth's atmosphere.
Date: 1961?
Creator: Harvey, Douglas G. & Brooks, Phillips M.
Partner: UNT Libraries Government Documents Department
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