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Data Telemetry Package Powered by Strontium-90 Fueled Generator: Final Report
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.
PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959
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.
PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960
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.
PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960
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.
PM-1 Nuclear Power Plant Program: Final Progress Report, September 1, 1962 Through Completion
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.
Special Welding Techniques : Final Summary Report
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.
Proceedings of the ANPP Reactor Analysis Seminar, October 11 and 12, 1960
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.
ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel
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.
Development of Iron-Aluminum Base Alloys for Gas Cooled Reactor Components: Second Quarterly Progress Report, June 1958
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.
PM Research and Development Task 1.0 : Core 2 Final Design Report
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.
SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 7, May 1, 1962-July 31, 1962
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.
Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report
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.
Fluidized Bed Reactor Study: Phase I - Feasibility
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.
PM-1 Nuclear Power Plant Program: 8th Quarterly Progress Report, December 1, 1960 to February 28, 1961
From abstract: The objective is the design, development, fabrication, installation and initial testing and operation of a prepackaged, air-transportable, pressurized water reactor nuclear power plant, the PM-1.
Feasibility Study of Water-Cooled Thermionic Nuclear Power Plant
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.
PM-3A Nuclear Power Plant Program
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.
ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959
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.
Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A
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.
Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Meteorological Station, SNAP-7C
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.
Upper Atmosphere Re-entry Study High Altitude Burnup: Volume 2
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.
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy: Final Report
From summary: This report describes the 10-watt Sr-90 thermoelectric generator, the dc-to-dc converter, batteries and the method of installation in the light buoy.
SNAP Programs : M-1 Monte Carlo Radioisotope Shielding Code : Final Report
From foreword: This final report summarizes the results of a project to develop a machine calculation code program using the Monte Carlo technique to compute radiation flux or dose rates from radioisotope sources.
Swaged Metal Fiber-UOâ‚‚ Fuel Element: Final Report
From introduction: The objectives of this program were to: study the variables of uranium dioxide, metal fibers and cladding material and determine the effects of swaging, develop thermal conductivity tests for small diameter rod-type elements, determine the thermal conductivity of various combinations of metal fibers and uranium dioxide, and select optimum combinations of the above variables to recommend for irradiation testing.
Strontium 90 Power Project: Final Summary Report
From summary: The primary purpose of this project is to determine the feasibility of converting reactor waste Strontium-90 into a safe and useful source of electrical energy. Secondary purpose is physical and environmental testing of the power conversion device or thermoelectric couples. This required actual fabrication of a 100-thermal-watt strontium titanate fuel element
PM-1 Nuclear Power Plant Program: 9th Quarterly Progress Report, March 1, 1961 to May 31, 1961
From abstract: The objective of the contract is the design, development, fabrication, installation initial testing and operation of a prepackaged, air transportable nuclear power plant, the PM-1.
Reactor Flow Studies : Full Scale Model Flow Tests
From foreword: This report contains the test results and analysis of test results of flow studies and reactor vessel internals. Tests were performed at, below, and above the PM-1 design flow rate to observe flow distribution and pressure drops within the reactor vessel, as well as the overall reactor vessel pressure drop.
PM-1 Reactor Core Final Design Report
From introduction: This report presents and evaluates the final design of the reactor core for the PM-1 Nuclear Power Plant. The design criteria required a pressurized water cooled and moderated core with a two-year life at design power and a positive shutdown margin under all conditions with either one control rod stuck completely out or with two control rods stuck in the operating condition.
PM Research and Development Program: 1st Quarterly Progress Report, April 15, 1961 to June 30, 1961
From summary: This report contains a description of the work accomplished during the first project quarter of the PM Research and Development Program, divided into six areas: core design development, plant design development, fuel element and core component development, critical experiments and zero power testing, reactor flow rates, and heat transfer tests.
SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 1, November 1, 1960-January 31, 1961
From summary: The SNAP 7 program is being conducted for the purpose of developing four radioisotope-fueled thermo-electric power generation systems. An important phase of this program is the processing of Strontium-90 into heat sources for these systems. The current effort involves the design and engineering analysis of two of the four thermo-electric generators.
SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 5, November 1, 1961-January 31, 1962
From introduction and summary: The SNAP 7 program is being conducted by the Martin Company for the purpose of developing four radioisotope-fueled thermo-electric power generation systems. The current program in its entirety covers: design, fabrication, test and delivery of four-radioisotope-fueled thermo-electric generator systems are to be designed to meet the rigorous environmental requirements of field use by the U.S. Coast Guard and the U.S. Navy.
Final Safety Analysis Report: SNAP III Thermoelectric Generator
From summary: An analysis has been performed to determine the ability of the fuel container to withstand the various thermal, mechanical and chemical forces imposed upon the generator by vehicle failures. Where theoretical analysis was impossible, and where experimental evidence was desired, capsules and generators were tested under simulated missile-failure conditions. Thus, the safety limits of SNAP III in a satellite application were defined.
PM-1 Nuclear Power Plant Program: Plant Performance Studies, Final Periodic Report, September 1, 1962 to December 31, 1962
From abstract: Data obtained during the performance testing of the PM-1 plant was compiled and evaluated. It is concluded from the data that the plant performance in general meets or exceeds specifications. Transient and steady-state electrical fluctuations are well within specified limitations. Heat balance data for both the primary and secondary systems agree reasonably well with design predictions. Radiation levels are below those anticipated.
SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 6, February 1, 1962-April 30, 1962
From introduction and summary: The prime effort on this contract has been directed toward: Manufacture, assembly and test of the 60-watt thermo-electric generators, procurement of SNAP-7D system components, installation and checkout of the Strontium-90 isotope process equipment.
SNAP 7D: stronium-90 fueled thermoelectric generator power source, thirty-watt U.S. Navy Floating Weather Station, final report
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 contract statement of work.
Snap 7B: Stronium-90 Fueled Thermoelectric Generator Power Source, Thirty- Watt U.S. Coast Guard Automatic Light Station. Final Report
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.
Final Safety Analysis Report: SNAP 1A Radioisotope Fueled Themonuclear Generator
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.
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