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Development of Liquid-Phase Sintering Techniques for Molybdenum Alloys. Final Report

Description: An envelope-type microstructure produced by liquidphase sintering techniques was used to develop ductiIe molybdenum-base alloys for sodium-cooled fast reactor application. A total of 105 compositions was examined; 21 showed evidence of room-temperature ductility, and a number of other compositions appeared promising. The prerequisites for obtaining ductile liquid-phase sintered materials were demonstrated. The most ductile alloys produced are based on the Mo--Pd--Cu and Mo --W--Ni--Fe systems. … more
Date: November 10, 1960
Partner: UNT Libraries Government Documents Department
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Rear crossheader fitting inspection B, D, and F Reactors

Description: Cavitational flow has been known to exist in-rear crossheader ``Parker`` fittings at B, D, and F Reactors for the last five or six years. Calculations showing initiation of cavitational flow as a result of high flow rates in the present fittings were verified by experimental data in 1954. A study is currently being conducted to determine the required plant modifications to obtain flow increases on the order of fifty percent above existing flows. This study and the results of preliminary tests t… more
Date: February 10, 1960
Creator: Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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The poison spline system

Description: No Description Available.
Date: March 10, 1960
Creator: Smithers, R. M.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Meeting: October 1960

Description: From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.
Date: November 10, 1960
Creator: Mravca, Andrew E.
Partner: UNT Libraries Government Documents Department
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Trip Report, Solar aircraft, May 26, 1960

Description: Discussions held with A. S. Stetson, General George Gordes and W. Compton going over technical aspects of Contract NO-S-935 for the research and development studies on coating materials for SNAP reactors.
Date: June 10, 1960
Creator: Henry, D.L.
Partner: UNT Libraries Government Documents Department
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Evaluation of Commercial Ceramic Coating for Short Time Protection of Columbium 1% Zirconium

Description: Abstract. Fourteen commercial enamel frits from five different manufacturers were tested to determine their abilities to protect Nb-1% Zr during the forging cycle in the temperature range of 1800 to 2300 deg F. One frit was found to afford good coverage and protection at 2200 deg F at times up to 5 hours of exposure. Adherence was excellent during upset forging of a coated Nb--1% Zr sample heated 45 minutes at 2200 deg F. Another frit afforded good protection and coverage at 1700 deg F. (auth)
Date: October 10, 1960
Creator: McGrath, D. W.
Partner: UNT Libraries Government Documents Department
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RADIATION LEVELS IN THE VICINITY OF THE PURIFICATION DEMINERALIZERS. CORE 1, SEED 1. Test Results T-641306

Description: BS>A test was performed to determine the activity build-up inside the 1AC and 1BD purification demineralizer concrete enclosure. A maximum radiation level of 1100 mr/hr was detected inside the 1AC demineralizer enclosure at a point 10.0 ft from the top. The maximum radiation level inside the 1BD enclosure was 700 mr/hr at a point 9.5 ft below the top. An analysis of data from five tests indicates that the extent of the activity build-up, as well as the level of activity, is definitely increasin… more
Date: October 10, 1960
Partner: UNT Libraries Government Documents Department
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Thermoelectric Nuclear Fuel Element Quarterly Progress Report for April- June 1960

Description: A hot-pressing system was designed and is adaptable for bomb melting experiments up to 2000 deg C. Two devices were constructed for measuring. One was designed to measure Seebeck coefficients, resistivities, and bond resistances of swaged and machined thermoelectric wafers and the other was designed to measure thermoelectric parameters of cylindrical thermoelectric pellets up to 1000 deg C. Design studies on a fission-fired thermoelectric generator were completed. Seebeck coefficient and resist… more
Date: July 10, 1960
Creator: Blankenship, W. P.; Goodspeed, R. C.; Markley, R. A. & Mitchell, P. V.
Partner: UNT Libraries Government Documents Department
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Synthesis and Fabrication of Refractory Uranium Compounds. Quarterly Report No. 4 for March 1 to April 30 and July 31, 1960

Description: Additional work on the synthesis and fabrication of uranium nitride produced an improved product free of oxide contamination as indicated by x-ray analysis. Further work to increase the density of the sintered pellets is needed. A stock of several pounds of stoichiometric uranium monocarbide was prepared by carbon reduction of uranium dioxide. Pellets having bulk densities ranging from 93 to 96% theoretical were obtained by cold pressing and sfntering. Initial experiments on the fabrication of … more
Date: August 10, 1960
Creator: Taylor, K. M.; Lenie, C. A.; Doherty, P. E. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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THE PREPARATION OF PLUTONIUM POWDER BY A HYDRIDING PROCESS-INITIAL STUDIES

Description: Micron-sized plutonium powder was produced by hydriding massive metal, then grinding and decomposing the hydride. An apparatus containing clean plutonium metal was evacuated to a pressure of 10 mu . Dry oxygen-free hydrogen was introduced and the apparatus placed in a furnace. After the reaction started, the apparatus was removed from the furnace and hydrogen added until the reaction was complete. The hydride was decomposed by heating to 400 deg C. Plutonium metal produced in this manner was po… more
Date: March 10, 1960
Creator: Stiffler, G. L. & Curtis, M. H.
Partner: UNT Libraries Government Documents Department
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Radioactive Waste Disposal System Periodic Radiation Monitoring Survey. Core I, Seed 1. Test Results T-612075. Section 2

Description: The radiation level of all permanently installed mom-tored points in the Hadioactive Waste Disposal Plant was determined periodically, and the effectiveness of shielding facilities in working areas at times during which the radiation level was above limits set up by Health Physics was checked. The radiation level in all areas surveyed was less than 5 mr/hr, which is the Health Physics' limitation for the Radioactive Waste Disposal Area. Any area with a level abeve 5 mr/hr is a controlled access… more
Date: October 10, 1960
Partner: UNT Libraries Government Documents Department
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Final Performance Tests of Two-Coolant-Region Sodium Pump Shaft Freeze- Selas

Description: A prototype of the two-coolant-region pump shaft freezeseals intended for application to the Hallam Power Reactor sodium pumps was fabricated. Tests under simulated reactor service conditions revealed satisfactory operation only when the lower of the two regions received heat from the circulating fluid (tetralin in the tests). With the inlet temperature of tetralin to the upper region of the seal maintained at 95 deg F and that to the lower region held in the range 240 to 285 deg F the sealfunc… more
Date: February 10, 1960
Creator: Streck, F.O.
Partner: UNT Libraries Government Documents Department
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HFIR RESPONSE TO VOID SWEPT INTO FLUX TRAP

Description: Flux excursions in the HFIR and the response of its safety system have been examined for the situations arising from voids swept into the flux trap with the cooling water. It was found that by limiting the addition of void reactivity to 00 or less, temperature coefficients alone can handle the excursion without damage to the core. Curves are given which show the safety system response necessary for larger additions of void reactivity. (auth)
Date: August 10, 1960
Creator: Stone, R.S.
Partner: UNT Libraries Government Documents Department
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ORNL FUEL CYCLE PROGRESS REPORT FOR PERIOD MARCH 15 to MAY 15, 1960

Description: A method for the preparation of high-density ThO/sub 2/ of the correct particle size for vibratory compaction is under development. The method being developed appears easily adaptable to remote operation. Pure ThO/sub 2/ made by this method was readily compacted to 86% of theoretical density by pneumatic vibration. Preparations of high-density mixed ThO/sub 2/ -UO/sub 2/ and UO/sub 2/ by this general method have been successfully carried out. Densification of arc-fused mixed oxide by a pneumati… more
Date: June 10, 1960
Creator: Ferguson, D E
Partner: UNT Libraries Government Documents Department
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SM-1 Reactor Vessel Penetrated Gasket Design and Test Report

Description: Mechanical compression tests were performed on gasket test specimens machined to the cross-sectional dimensions of a stainless steel (Type 304) ring type gasket to be installed in the SM-1 reactor pressure vessel. Testing the mechanical properties of the gasket specimens under varying loads, and subsequent sectioning and inspection of specimens for adequacy of welded and brazed joints, gave the following results: (1) a penetration scheme involving five 0.070-in. diam. holes, spaced 1/4 in. cent… more
Date: June 10, 1960
Creator: Gebhardt, F. G.
Partner: UNT Libraries Government Documents Department
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THE PEBBLE BED REACTOR PROGRAM. Current Fuel Element Developments and Their Effects on the Pebble Bed Reactor Development Program

Description: Recent fuel element irradiations demonstrated the structural integrity of spherical uranium-graphite fuel elements at burn-ups in excess of the design requirements of a 125 Mw(e) Pebble Bed Reactor (PBR) power plant. Other irradiations indicated the successful development of a coated fuel particle which permits fabrication of fuel elements meeting the PBR design objectives of a fission-product release rate (R/B) ? /sup 10-6/. beta plus gamma system activity in a 125 Mw(e) PBR is 490 c, assuming… more
Date: May 10, 1960
Partner: UNT Libraries Government Documents Department
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Synthesis and Fabrication of Refractory Uranium Compounds. Monthly Progress Report No. 8 for April 1 Through April 31, 1960

Description: The effort on uranium silicide during the repent period was equally divided between synthesis and fabrication. The goal for the synthesizing effort was to make U/sub 3/8i/sub 2/ of higher purity than that made in the past, and the goal for the fabrication effort was to make pellets of density higher than 93%. Both goals were achieved. Experiments in simultaneous synthesis and fabrication of uranium monocarbide are reported in which mixtures of uranium powder and carbon were hot pressed. Sinteri… more
Date: May 10, 1960
Creator: Taylor, K. M.; Lenie, C. A.; Doherty, P. E.; Hailey, L. N. & Keaty, T. J.
Partner: UNT Libraries Government Documents Department
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14-Inch Swing Check Valve Test

Description: The check valve for the Hallam Power Reactor uses a knife-edge bearing for the flapper in place of the usual journal-type bearing. Mechanical cycling in sodium at 600 deg F was used to check operation of this bearing. A total of 309 mechanical cycles was completed with no apparent malfunctioning of the valve. Measured leskage rates were 0.46 gpm at 0.93 psig, 0.73 gpm at 3.4 psig. and 0.32 gpm at 5.9 psig. (M.C.G.)
Date: February 10, 1960
Creator: Cygan, R.
Partner: UNT Libraries Government Documents Department
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FABRICATION OF TANTALUM CAPSULES FOR LAMPRE I REACTOR

Description: Tantalum fabrication methods primarily for use as a container for molten plutonium are described. One method involved the rolling of a Ta billet into sheet of the desired age, cutting a circular blank, and deep drawing the tantalum blank through successive stages into the desimed shape. Another method used for the fabrication of Ta containers consisted of a combination of impact extrusion and ironing. This method involved the extrusion of the cast billet into rod, swaging the rod to a suitable … more
Date: June 10, 1960
Creator: Hanks, G.S. & Taub, J.M.
Partner: UNT Libraries Government Documents Department
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Evaluation of Calandria, Thimble, and Canned-Moderator Concepts for Sodium Graphite Reactors

Description: In efforts to improve the neutron economy and lower the capital costs of sodium graphite reactors, several methods of separating the sodium and graphite were investigated including the calandria, the thimble, and the canned moderator reactors. An analysis including nuclear, heat transfer, and economic comparisons was made of these SGR concepts. Based upon neutron economy and feasibility of core fabrication, the calandria concept appears to offer the greatest potential for improvement in 8GR des… more
Date: June 10, 1960
Creator: Reed, G.L.
Partner: UNT Libraries Government Documents Department
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