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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.