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RADIOISOTOPE FUELED AUXILIARY POWER UNIT. Quarterly Progress Report No. 1, January 2-April 2, 1957

Description: Progress on an isotope-fueled auxiliary power unit is reported. Based on the power requirements of 260 W, it was concluded that Ce/sup 144/ should be used as fuel. Estimates were made of fuel availability and unit cost and weight at power levels of 133, 300, 500, and 1000 W(e). Fuel development, boiler development, system and operational considerations, and the power conservation system are discussed. (M.C.G.)
Date: October 31, 1962
Creator: Silverstein, C.C. & Behmer, R.E. comps.
Partner: UNT Libraries Government Documents Department
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SNAP-27 follow-on quality assurance plan

Description: The Quality Plan for the SNAP-27 Follow-On Program describes the manner in which the Isotope Power Systems Operation of the General Electric Space Division will control product quality. NASA NHB5300.4 (1B) and AEC QASL-SNAP-1 and 2 have been used as guides in the development of this plan and, upon approval by the AEC, this plan will serve as a policy document to be utilized in implementing the SNAP-27 Follow-On Quality Program.
Date: September 23, 1970
Creator: Mason, F.C.
Partner: UNT Libraries Government Documents Department
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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
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SNAP-23A Program. Phase I. Thermoelectric Converter Development Program. Monthly report, April 1969

Description: The following activities were conducted during the month of April 1969: continued effort toward completion of the detailed design of the PMC-2 converter, conducted technical liaison with Westinghouse with respect to the power cable specification, conducted potting test for evaluation of material suitable for SNAP-23A converter PMC-2 leak specification, and completed design of parts for the Weld Development Program. Test data evaluation and analysis were performed on the following long-term test devices during February 1969: experimental mockup converter No. 2 (EMC-2), experimental mockup converter No. 3 (EMC-3), prototype mockup converter No. 1B (PMC-1B), 10-couple modules 1 and 3, 10-couple modules 5 through 12 on design-of-experiments tests, 6-couple module 23A3, and converter 23 P-2.
Date: May 15, 1969
Partner: UNT Libraries Government Documents Department
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Data sheets for PPO radioisotopic fuel

Description: PPO is the acronym for Pure Plutoniunn Oxide. The thermal energy of this fuel results from the radioactive decay of /sup 238/ Pu this energy is converted into usable electric power for space probe or other applications. The basic fuel module associated with the current MHW heat source is a PPO sphere 1.465 plus or minus 0.015 in. in dia and containing 100 plus or minus 2 thermal watts. The spheres are individually encapsulated and then assembled into geometric arrays to form the working heat source. The following document lists certain properties of PuO/sub 2/ with emphasis on behavior at the proposed operational conditions being discussed. Since many of the desired properties are still being determined, the information is preliminary in nature and will be revised periodically. This report is the first revision of LA-5160-MS (issued 2/ 73) and incorporates additional and more specific data. (auth)
Date: December 1, 1973
Creator: Keenan, T. K.; Kent, R. A.; Mulford, R. N. R. & Shupe, M. W.
Partner: UNT Libraries Government Documents Department
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BEARING MATERIALS COMPATIBILITY FOR SPACE NUCLEAR AUXILIARY POWER SYSTEMS

Description: A program to evaluate materials for suitability ss exposed bearings on nuclear auxiliary power systems (SNAP Program) for space vehicles is reported. Friction coef ficients of material combinations in a 10/sup -6/ mm Hg vacuum at 1000 deg F for 200 hr were measured. Seven combinations found to have friction coefficients less than 0.50 are: graphite-Haynes 90; graphite-Stellite No. 3; graphiteAl/sub 2/O/sub 3/ (sprayed); Al/sub 2/O/sub 3/ (sprayed)-Cr/sub 3/ C/sub 2/ (spr ayed); Al/sub 2/O/sub 3/ (sprayed)-TiC; Al/sup 2/O /sub 3/ (solid)-3-F- 12; and Al/sub 2/O/sub 3/ (solid)N-12. (auth)
Date: September 1, 1961
Creator: Kurzeka, W.J.
Partner: UNT Libraries Government Documents Department
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Mass spectrometric determination of $sup 18$O/$sup 16$O ratios to locate the source of oxygen in SNAP fuel capsule components

Description: The successful application of a mass spectrometric method to determine the source of oxygen diffusion into the container material of a radioisotopic fuel capsule is described. The source was chiefly the oxide fuel (/sup 238/PuO/ sub 2/) and not the atmosphere. This could be accomplished by determining the / sup 18/O//sup 16/O ratio in the tantalum alloy material, because the /sup 18/O content of the fuel had been reduced to minimize alpha -n reactions. The /sup 18/O//sup 16/O ratio was ~5.5 x 10/sup -4/ for fuel as compared with 2 x 10/sup - 3/ for air. The radiochemical method, based on an alpha -n reaction, could not be applied because of the very low alpha -particle flux in the liner material. (auth)
Date: February 1, 1974
Creator: Smith, M.E. & Waterbury, G.R.
Partner: UNT Libraries Government Documents Department
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SNAP II Power Conversion System Topical Report No. 16, 2500-Hour Endurance Test of Mercury Rankine Cycle Power System

Description: SNAP 1 is the designation for the 0.5-kw nuclear auxiliary power supply intended for application in a satellite. SNAP 1 was designed to convert thermal energy from the decay of a radioisotope into electrical energy using a Rankine engine with mercury as the working fluid. A successful 2500-hour endurance test is described of a complete developmental version of the SNAP 1 power conversion system utilizing a prototype turbomachinery package, an electrically heated boiler, and an air-cooled condenser. Indications from the data obtained during the test and from inspection of the system following the test were that many more hours of satisfactory operation could have been obtained on all major system components except the rotating unit pump. The mercury-lubricated bearings, the turbine, and the alternator, all demonstrated excellent endurance capability. Based on previous component tests, it is concluded that the pump performance deterioration was caused by air entrainment in the liquid Hg. (auth)
Date: January 1, 1961
Creator: Grevstad, P.E.
Partner: UNT Libraries Government Documents Department
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