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SNAP I POWER CONVERSION SYSTEM BEARINGS DEVELOPMENT. Period covered: February 1, 1957 to June 30, 1959

Description: Development of bearings for use in the SNAP I power conversion system is described. Liquid mercury, lubricated hydrosphere bearings were selected. Design and performance data are given along with conclusions. (J.R.D.)
Date: June 20, 1960
Creator: Meredith, R.; Ono, G.Y. & Reemsnyder, D.C.
Partner: UNT Libraries Government Documents Department

A PARAMETRIC STUDY OF CERTAIN LOW-MOLECULAR-WEIGHT COMPOUNDS AS NUCLEAR ROCKET PROPELLANTS. V. METHANE

Description: A parametric investigation was made of a series of lowmolecular-weight, high-hydrogen-content compounds as propellants for nuclear-powered rockets. The chemical compounds include H/sub 2/, NH/sub 3/, H/sub 2/0, LiH, CH/sub 4/, and CH/ sub 3/OH. A two-part computational program was carried out for each compound; the results for methane are presented in both tabular and graphic form. The results of the first part of the program are presented in static form, that is, by the conventional Mollier diagram, in which specific enthalpy is plotted against specific entropy, with cross plots of temperature, pressure, and molecular weight. The results of the second part of the program are presented in dynamic form by a series of diagrams in which specific impulse is plotted against pressure, with cross plots of chamber temperature, exhaust temperature, and rocket-nozzle area. It was assumed that the propellant gas, starting with a nonzero chamber velocity, maintained instantaneous chemical equilibrium composition as it expanded isentropically through a de LavaI nozzle. (auth)
Date: August 1, 1961
Creator: Krieger, F.J.
Partner: UNT Libraries Government Documents Department

STATE OF NUCLEAR TECHNOLOGY-JANUARY 1962

Description: Events in nuclear technology in 1961 are reviewed. The SL-1 incident, operation of the Yankee plant, restarting of the Dresden plant, contributions to the state of water reactor technology, transitions to private industry, dry criticality in EBR-II, startup of Los Alamos Molten Plutonium Reactor Experiment (LAMPRE), successful Tory tests, performance of SNAP reactor tests, and use of radioisotope-powered electric source in Transit IV A are discussed. (M.C.G.)
Date: November 1, 1961
Creator: Crewe, A.; Lawreski, S. & Spinrad, B.I.
Partner: UNT Libraries Government Documents Department

MATERIALS COMPATIBILITY OF SNAP FUEL COMPONENTS DURING SHIPMENT IN 9975 PACKAGING

Description: Materials Science and Technology has evaluated materials compatibility for the SNAP (Systems for Nuclear Auxiliary Power) fuel for containment within a 9975 packaging assembly for a shipping period of one year. The evaluation included consideration for potential for water within the convenience can, corrosion from water, galvanic corrosion, tape degradation, and thermal expansion risk. Based on a review of existing literature and assumed conditions, corrosion and/or degradation of the 304 stainless steel (SS) Primary Containment Vessel (PCV) and the 304 stainless steel convenience cans containing the SNAP fuel is not significant to cause failure during the 1 year time shipping period in the 9975 packaging assembly. However, storage beyond the 1 year shipping period has not been validated.
Date: November 14, 2006
Creator: Vormelker, P
Partner: UNT Libraries Government Documents Department

Experimental Criticality Benchmarks for SNAP 10A/2 Reactor Cores

Description: This report describes computational benchmark models for nuclear criticality derived from descriptions of the Systems for Nuclear Auxiliary Power (SNAP) Critical Assembly (SCA)-4B experimental criticality program conducted by Atomics International during the early 1960's. The selected experimental configurations consist of fueled SNAP 10A/2-type reactor cores subject to varied conditions of water immersion and reflection under experimental control to measure neutron multiplication. SNAP 10A/2-type reactor cores are compact volumes fueled and moderated with the hydride of highly enriched uranium-zirconium alloy. Specifications for the materials and geometry needed to describe a given experimental configuration for a model using MCNP5 are provided. The material and geometry specifications are adequate to permit user development of input for alternative nuclear safety codes, such as KENO. A total of 73 distinct experimental configurations are described.
Date: December 19, 2005
Creator: Krass, A.W.
Partner: UNT Libraries Government Documents Department

Water Sorption and Radiolysis Studies for Neptunium Oxides

Description: Plans are to convert the {sup 237}Np that is currently stored as a nitrate solution at the Savannah River Site to NpO{sub 2} and then ship it to the Y-12 National Security Complex in Oak Ridge for interim storage. This material will serve as feedstock for the {sup 238}Pu production program, and some will be periodically shipped to the Oak Ridge National Laboratory (ORNL) for fabrication into targets. The safe storage of this material requires an understanding of the radiolysis of moisture that is sorbed on the oxides, which, in turn, provides a basis for storage criteria (namely, moisture content). A two-component experimental program has been undertaken at ORNL to evaluate the radiolytic effects on NpO{sub 2}: (1) moisture uptake experiments and (2) radiolysis experiments using both gamma and alpha radiation. These experiments have produced two key results. First, the water uptake experiments demonstrated that the 0.5 wt % moisture limit that has been typically established for similar materials (e.g., uranium and plutonium oxides) cannot be obtained in a practical environment. In fact, the uptake in a typical environment can be expected to be at least an order of magnitude lower than the limit. The second key result is the establishment of steady-state pressure plateaus as a result of the radiolysis of sorbed moisture. These plateaus are the result of back reactions that limit the overall pressure increase and H{sub 2} production. These results clearly demonstrate that 0.5 wt % H{sub 2}O on NpO{sub 2} is safe for long-term storage--if such a moisture content could even be practically reached.
Date: February 3, 2004
Creator: Icenhour, A.S.
Partner: UNT Libraries Government Documents Department

SNAP 7 PROGRAM--TASK 8--STRONTIUM-90 FUELED THERMOELECTRIC GENERATOR DEVELOPMENT. Quarterly Progress Report No. 7, May 1 through July 31, 1962

Description: The effort on SNAP 7A and 7C was confined to operating the reliability model. There were fluctuations in output power that can be attributed to variations in the operating parameters, plus an increase in the internal resistance. In the SNAP 7B project the second 60-watt generator was completed and has undergone the beginning-of-life (maximum input, helium gas) portion of the parametric tests. The performance was nearly identical to that of the first 60-watt generator. The unit will be used with the SNAP 7B system. The installation concept for the SNAP 7B system was approved by the U. S. Coast Guard. The generator is to be housed in a finned aluminum container that will provide the required radiator surface. This container will be filled with a water- ethylene glycol mixture that is necessary to transfer the heat from the generator into the container. The battery-converter compartment is an integral part of the container lid. During the time the entire SNAP 7D system was subjected to shock and vibratlon tests, no mechanical or functional deficiencies were detected. The required temperature tests followed the mechanical tests. During this period the complete system was operated at maximum intermediate and minimum temperatures. Design objectives were satisfied throughout the test. The SNAP 7D generator was fueled at Oak Ridge National Laboratory (ORNL) on June 12, 1962, with a total thermal input of 1435 watts. The iueled generator was returned and integrated with the system. The system was demonstrated and accepted on July 3, 1962. (auth)
Date: October 31, 1963
Creator: McDonald, W.A.
Partner: UNT Libraries Government Documents Department

Correlation of Liquid Fraction in Two-Phase Flow With Application to Liquid Metals

Description: A generalized correlation for the liquid fraction in twophase flow is presented which is proposed for use with all iluids, including liquid metals. The correlation is based on isothermal, two-phase, two-component liquid fraction data for liquid Hg--N/sub 2/ and water-air. Liquid fraction is shown to be a function of the Martinelli flow modulus and liquid/gas density and viscosity ratios. Good correspondence is indicated between the liquid fraction predicted by this correlation and the Martinelli-Nelson correlation for steam, experimental data for steam, and experimental data for Santowax R. Prediction of liquid fraction by this method is shown for Na, K, Rb, and Hg. Application of the method to boiling Hg, for a range of temperatures and exit qualities, is demonstrated for SNAP systems. (auth)
Date: April 15, 1963
Creator: Baroczy, C. J.
Partner: UNT Libraries Government Documents Department

Solubility study of strontium fuel compounds

Description: Strontium titanate, distrontium titanate, and strontium fluoride have been considered as isotopic fuels in thermoelectric generators for space and terrestrial applications. Evaluation of the radiobiological and radioecological effects of accidental release of /sup 90/Sr on land, in water, and in air requires a knowledge of the dissolution rates of the fuel in fresh water, salt water, and dilute HCl. Results of a study to investigate the behavior of these strontium fuel forms in the different test solutions are presented. (TFD)
Date: June 1, 1966
Creator: Gray, J. H.
Partner: UNT Libraries Government Documents Department

INVESTIGATION OF CAVITATION DAMAGE OF MECHANICAL PUMP IMPELLERS OPERATING IN LIQUID METAL SPACE POWER LOOPS. Quarterly Progress Report No. 2, October 1, 1963-December 31, 1963

Description: Water testing of the RI-7C3 impeller in the Pt-2 test stand was completed. Still photographs and movies showed that a vortex was present on the leading edge tip of all blades at NPSH values up to 150 ft at all five test flows of 660, 680, 700, 720, and 740 gpm. Sound data showed a possible correlation with the cavitation performance of the impeller. The sound intensity increased until the tip vortices entered the flow channels and then decreased, reaching a minimum just before head loss occurred. As the head fell off, the sound intensity increased to a level as great or greater than the previous maximum. The TP-1 turbopump detail parts required to complete the assembly of the pump in its modified form were completed. The turbopump was assembled with the tested impeller and installed in the PT-4 water pump test stand. The pump was operated at low speed to assure proper seating of the seals and testing started. The PT-6 liquid metal test stand construction drawings were completed. Construction of the test stand was started by disassembling, cleaning, and acid pickling the entire loop piping. Reassembly of the test loop was started. (N.W.R.)
Date: January 15, 1964
Creator: Kulp, R.S. & Altieri, J.V.
Partner: UNT Libraries Government Documents Department