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PM Research and Development Program: 1st Quarterly Progress Report, April 15, 1961 to June 30, 1961

Description: 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.
Date: March 1962
Creator: Baer, R. L.
Partner: UNT Libraries Government Documents Department
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PM-1 Reactor Core Final Design Report

Description: 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.
Date: January 1962
Creator: Bagley, R. O.; Cox, F. H.; Carnasale, A. & Vener, H.
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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Final Safety Analysis Report: SNAP III Thermoelectric Generator

Description: 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.
Date: June 1960
Creator: Hagis, W. & Dix, George P.
Partner: UNT Libraries Government Documents Department
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Swaged Metal Fiber-UO₂ Fuel Element: Final Report

Description: 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.
Date: January 1960
Creator: Kane, John
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-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-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
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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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SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 5, November 1, 1961-January 31, 1962

Description: 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.
Date: 1962
Creator: McDonald, W. A. & Kershaw, W. L.
Partner: UNT Libraries Government Documents Department
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SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 6, February 1, 1962-April 30, 1962

Description: 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.
Date: 1962
Creator: McDonald, W. A. & Kershaw, W. 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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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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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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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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