Data Telemetry Package Powered by Strontium-90 Fueled Generator: Final Report (open access)

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.
Date: September 1961
Creator: unknown
System: The UNT Digital Library
PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959 (open access)

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.
Date: March 1960
Creator: Martin Company. Nuclear Division.
System: The UNT Digital Library
PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960 (open access)

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.
Date: April 5, 1960
Creator: Martin Company. Nuclear Division.
System: The UNT Digital Library
PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960 (open access)

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.
Date: July 5, 1960
Creator: Martin Company. Nuclear Division.
System: The UNT Digital Library
PM-1 Nuclear Power Plant Program: Final Progress Report, September 1, 1962 Through Completion (open access)

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.
Date: July 15, 1963
Creator: unknown
System: The UNT Digital Library
Proceedings of the ANPP Reactor Analysis Seminar, October 11 and 12, 1960 (open access)

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.
Date: January 1961
Creator: O'Brien, J. F.
System: The UNT Digital Library
ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel (open access)

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.
Date: May 1962
Creator: Welshans, L.
System: The UNT Digital Library
PM Research and Development Task 1.0 : Core 2 Final Design Report (open access)

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.
Date: April 1963
Creator: Russo, F.; Brittain, W.; Lightner, R. & Baer, R.
System: The UNT Digital Library
SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 7, May 1, 1962-July 31, 1962 (open access)

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.
Date: 1962
Creator: McDonald, W. A.
System: The UNT Digital Library
PM-1 Nuclear Power Plant Program: 8th Quarterly Progress Report, December 1, 1960 to February 28, 1961 (open access)

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.
Date: April 6, 1961
Creator: Sieg, J. S.
System: The UNT Digital Library
Feasibility Study of Water-Cooled Thermionic Nuclear Power Plant (open access)

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.
Date: November 1962
Creator: Martin Company. Nuclear Division.
System: The UNT Digital Library
PM-3A Nuclear Power Plant Program (open access)

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.
Date: July 21, 1961
Creator: Martin Company. Nuclear Division.
System: The UNT Digital Library
Final Safety Analysis Report: SNAP 1A Radioisotope Fueled Themonuclear Generator (open access)

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.
Date: June 30, 1960
Creator: Dix, George P.
System: The UNT Digital Library
Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A (open access)

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.
Date: February 1962
Creator: Brooks, Phillip M. & Keegan, James J.
System: The UNT Digital Library
Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Meteorological Station, SNAP-7C (open access)

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.
Date: 1962
Creator: Brooks, Phillip M. & Keegan, James J.
System: The UNT Digital Library
Upper Atmosphere Re-entry Study High Altitude Burnup: Volume 2 (open access)

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.
Date: 1961?
Creator: Harvey, Douglas G. & Brooks, Phillips M.
System: The UNT Digital Library
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy: Final Report (open access)

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.
Date: February 2, 1962
Creator: unknown
System: The UNT Digital Library
SNAP Programs : M-1 Monte Carlo Radioisotope Shielding Code : Final Report (open access)

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.
Date: May 1, 1962
Creator: Kniedler, M. J. & Wilson, R. J.
System: The UNT Digital Library
Swaged Metal Fiber-UO₂ Fuel Element: Final Report (open access)

Swaged Metal Fiber-UO₂ 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.
Date: January 1960
Creator: Kane, John
System: The UNT Digital Library
Strontium 90 Power Project: Final Summary Report (open access)

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
Date: March 1960
Creator: unknown
System: The UNT Digital Library
PM-1 Nuclear Power Plant Program: 9th Quarterly Progress Report, March 1, 1961 to May 31, 1961 (open access)

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.
Date: July 10, 1961
Creator: O'Brien, J. F.
System: The UNT Digital Library
Reactor Flow Studies : Full Scale Model Flow Tests (open access)

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.
Date: June 1961
Creator: Taylor, W. J.; Starr, I. & Baer, R. L.
System: The UNT Digital Library
PM-1 Reactor Core Final Design Report (open access)

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.
Date: January 1962
Creator: Bagley, R. O.; Cox, F. H.; Carnasale, A. & Vener, H.
System: The UNT Digital Library
PM Research and Development Program: 1st Quarterly Progress Report, April  15, 1961 to June 30, 1961 (open access)

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.
Date: March 1962
Creator: Baer, R. L.
System: The UNT Digital Library