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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

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.; Brittan, W.; Lightner, R. & Baer, R.
Partner: UNT Libraries Government Documents Department

SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 1, November 1, 1960-January 31, 1961

Description: 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.
Date: June 1961
Partner: UNT Libraries Government Documents Department

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
Partner: UNT Libraries Government Documents Department

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
Partner: UNT Libraries Government Documents Department

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

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

Strontium 90 Power Project: Final Summary Report

Description: 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
Partner: UNT Libraries Government Documents Department

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

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
Partner: UNT Libraries Government Documents Department

Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report

Description: 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.
Date: April 1959
Creator: Tate, Frank
Partner: UNT Libraries Government Documents Department

Fluidized Bed Reactor Study: Phase I - Feasibility

Description: 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.
Date: February 1959
Partner: UNT Libraries Government Documents Department

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

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

PM-1 Nuclear Power Plant Program Parametric Study Report

Description: The study deals with narrowing the range of parameters prior to preliminary design of the PM-1, a factory prepackaged, air-transportable, pressurized water nuclear power plant. The plant is to produce 1000 kw of net electrical power and 7 x 10/sup 6/ Btu/hr of space heat that is suitable for use with a central heating system. The data and conclusions resulting from the parametric study will provide the basis for the preliminary design of the PM-1 power plant. (W.D.M.)
Date: September 1, 1959
Creator: Sieg, J. S.
Partner: UNT Libraries Government Documents Department

Preliminary Operationai Hazards Summary Report for the Task 2 Thermoelectric Generator

Description: The operational hazards associated with the use of an isotope-fueled auxiliary power unit for a satellite mission are described. The effects of missile about on the generator are discussed. The generator design is described, and the properties of the various fuel forms are investigated. The characteristics of the fuel capsules and the provisions for biological shielding are also described. Integration of the generator into a typical missile system is discussed. Hazards and procedures of transporting and handling the fuel cores from fabrication to launchlng are considered. Aborted missions are defined, and the forces acting on the generator during abort are described. (W.D.M.)
Date: December 1, 1959
Creator: Dix, G. P., Jr.
Partner: UNT Libraries Government Documents Department

Preliminary Operational Safety Report for the Task 5.6 Thermoelectric Generator

Description: The operational hazards associated with the use of a plutonium-fueled thermoelectric generator in a terrestrial satellite are evaluated. It appears that the plutonium fuel can be consumed and dispersed at high altitude during reentry, following a successful mission. As an alternative, however, since the fuel (Pu/sup 238/) is an alpha emitter with a long half life, it appears that random intant recntry following a suceessful mission is feasible. As a precaution against aborted missions, the launch azimuth should be over water as much as possible to avoid impact or dispersion in areas of signifieant population density. It is recommended that the fuel and generators be transported by air carrier to preclude local restrictions of ground transport and to provide better statistical safety. The transport phase poses a very minor safety problem. (auth)
Date: May 1, 1960
Creator: Knighton, D.
Partner: UNT Libraries Government Documents Department

Preliminary Safety Analysis Low Power Cerium-144 Generator

Description: A safety analysis of small Ce/sup 144/ fueled thermoelectric generators for use in terrestrial satellite systems is given. The Ce/sup 144/ fuel is enclosed in a capsule of Haynes25, which is to be maintained at 580 deg C during operation. Lead telluride thermoelectric elements surround the capsule and are contained in an outer stainless steel shell. In one configuration a second shell filled with Hg is used for biological shielding. The biological shield reduces the direct radiation dose from decay gammas and bremsstrahlung to 90 mr/hr at 3 ft. The integrity of the fuel capsule under the spectrum of launch failure forces is considered. These forces include internal pressure, external forces from shock overpressures and impact, corrosion, and propellant fires. Following successful missions, the fuel is to be released in the stratosphere at a time when the source strength is about 4000 c. Resultant ground concentrations would be 2 x 10-/sup 9/c/sq mile and 0.053 mc/sq km for temperate zone and prompt stratospheric releases, respectively. (C.J.G.)
Date: June 1, 1960
Partner: UNT Libraries Government Documents Department

Radioactive Materials Laboratory Safety Report, Martin Nuclear Facility, Quehanna Site

Description: A description is given of the safety features and the major alterations to be performed prior to occupancy. The evaluation was made in support of fubrication work on the production of safe isotopic power sources from Cm/sup 242/ and Sr/sup 90/. The chemical, nuclear, and radiobiological properties of Cm/sup 242/ and Sr/sup 90/ are outlined. The projected physical fiow of materials for production of the isotopic power souroes is schematically given. An evaluation of the malfunctions, operational hazards, and remedial health physics procedures is presented. The analysis and evaluation of postulated maximum credible incidents are demonstrated. (B.O.G.)
Date: September 1, 1960
Partner: UNT Libraries Government Documents Department

SNAP 7 Program--Task 8--Strontium-90 Fueled Thermoelectric Generator Development. Quarterly Report No. 6, February 1 Through April 30, 1962

Description: Manufacture, assembly, and pararmetric testing of the first 60-watt thermoelectric generator were completed. All of the Sr-90 fuel process equipment was installed. Equipment checkouts and process dry runs have indicated a number of problems. The problems will probably cause a slight delay in hot operation; however, it is expected that schedule commitments in completing the fuel for the SNAP-7B system will be met. The power output of the Coast Guard SNAP-7A system is decreasing much faster than anticipated. A comparison of power output and hot and cold junction temperature readings with parametric operational data shows that the generator is performing as predicted. A plot of the decay in hot junction temperature (cold junction temperature approximately constant) indicates that the isotope fuel had too much Sr-89 and, therefore, too little Sr- 90. Restoration would consist of changing the high conducting inert gas, helium, to a mixture of helium and argon which has better thermal insulating properties. (auth)
Date: October 31, 1962
Creator: McDonald, W. A.
Partner: UNT Libraries Government Documents Department

SNAP 7 Program Task 8--Strontium-90 Fueled Thermoelectric Generator Development. Quarterly Progress Report No. 3, May 1, 1961 Through July 31, 1961

Description: The SNAP 7 program is being conducted for the purpose of developing 4 radioisotope fueled thermoelectric power generation systems. An important phase of this program is the processing of Sr/sup 90/ into heat sources for these systems. The thermoelectric reliability breadboard model and the operating model of the 10-watt thermoelectric generator were assembled and prepared for tests. The SNAP 7B and 7D 60-watt thermoelectric generators were designed, materials were received, and fabrication of components was initiated. Fuel process engineering, nuclear chemistry audit, and manufacturing fuel processing equipment achievements are discussed. (M.C.G.)
Date: October 31, 1962
Creator: West, W.
Partner: UNT Libraries Government Documents Department