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.

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.

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.

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.

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.

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.

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.

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

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.

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.

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.

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.

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.

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: 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 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 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 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 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.