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Differential Thermal-Expansion Effects on Brazed Joints

Description: Abstract: "Differential thermal-expansion effects in brazed joints involving Type 310 stainless steel and GE-62 brazing alloy were investigated. The work included dilation and modulus-of-elasticity measurements using homogenous cast specimens and observations on bimetallic cantilevers made of the two constituents. No anomalies were found, although there were irregularities in the expansion of the brazing alloy which were ascribed to a solubility phenomenon. The elastic modulus of the brazing al… more
Date: September 4, 1953
Creator: Saller, Henry A.; Baroody, Eugene Michael, 1914-1982; Deem, H. W.; Stacy, J. T. & Klebanow, H. L.
Partner: UNT Libraries Government Documents Department
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Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors

Description: From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."
Date: September 8, 1953
Creator: Crooks, R. C.; Snyder, M. J. & Clegg, J. W.
Partner: UNT Libraries Government Documents Department
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Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops

Description: From introduction: "This report presents the results of an experimental program to evaluate engineering problems which might be encountered when circulating NaOH-UO3 slurry through a thermal cycle."
Date: September 15, 1953
Creator: Stang, J. H.; Lagedrost, J. F.; Simons, E. M. & Dayton, R. W.
Partner: UNT Libraries Government Documents Department
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Ternaries of the eutectic uranium-chromium alloy

Description: A report about a study about the effect of small additions of iron, nickel, and manganese to the uranium - 5 wt % chromium eutectic alloy.
Date: 1953
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, A. A.
Partner: UNT Libraries Government Documents Department
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Temperature distributions in a reactor fuel plate

Description: Report detailing local heat-transfer coefficients as they relate to temperature distribution in reactor fuel plates.
Date: 1953
Creator: Chastain, Joel W.; Long, J. K.; Redmond, R. F.; Grimble, R. E. & Dayton, R. W.
Partner: UNT Libraries Government Documents Department
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The Effectiveness of Spray Cooling

Description: Abstract: "A possible method of cooling a liquid-fuel reactor is by spraying liquid metal through the liquid fuel, and then circulating the liquid metal through a heat exchanger. To evaluate the effectiveness of this cooling method, a few simple experiments were made with mercury sprayed through water. On the basis of the results, it was concluded that this method was intrinsically a low-power-density method, which could not find application except where a low fissionable-material inventory was… more
Date: October 1, 1953
Creator: Dayton, R. W.; Allen, C. M. & Miller, N. E.
Partner: UNT Libraries Government Documents Department
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Uranium Occurrences in the Golden Gate Canyon and Ralston Creek Areas, Jefferson County, Colorado

Description: From abstract: Pitchblende, associated with base-metal sulfides, has been found at eight localities in the northern part of Jefferson County, Colo., in shear zones that cut pre-Cambrian metamorphic and igneous rocks, chiefly hornblende gneiss, biotite schist, and granite pegmatite. The pitchblende deposits, with one exception, are in major shear zones that contain vein-like bodies of carbonate-rich breccia. The breccia bodies range from 1 to 5 feet in thickness and are related probably to the L… more
Date: January 1953
Creator: Adams, John W.; Gude, Arthur J., III & Beroni, E. P.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on 1952 Field Investigations in Wet Mountains, Colorado

Description: From page 3: A metallogenic province containing thorium in veins in pre-Cambrian rocks along the western slope of the Wet Mountains, Colo. found by the Reconnaissance Group of the U. S. Geological Survey during the summer of 1950,was revealed by the discovery during fiscal-years 1951-1952 of seventeen radioactive deposits scattered along a north-northwest linear distance of twenty miles. All the thorium occurrences were found within terrain that has never been geologically mapped. Three of the … more
Date: 1953
Creator: Singewald, Q. D.; Christman, Robert A. & Brock, M. R.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on the Mineral Hill Monazite Deposits, Lemhi County, Idaho

Description: From abstract: The Mineral Hill monazite deposits, 3 to 5 miles northeast of the town of Shoup, Lemhi County, Idaho, were investigated by the U. S. Geological Survey in July 1952. The deposits are replacement veins and lenses along shears in a pendant, principally of pre-Cambrian biotite gniess, about 4 to 5 miles in size and enclosed by granite of the Idaho batholith. The veins consist predominantly of calcite, monazite, and allanite, and contain minor quantities of barite, magnetite, rutile, … more
Date: April 1953
Creator: Sharp, W. N. & Cavender, W. S.
Partner: UNT Libraries Government Documents Department
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Wind-Tunnel Investigation of a 1/60-Scale Model of the Republic MX-1554 Airplane at a Mach Number of 2.85

Description: Report presenting the results of an investigation to determine the static longitudinal and lateral stability and control characteristics of a model of the Republic MX-1554 airplane at a specified Mach and Reynolds number. No analysis was provided in the paper in order to expedite publication.
Date: March 18, 1953
Creator: Dickey, Robert R. & Spahr, J. Richard
Partner: UNT Libraries Government Documents Department
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Use of reactor effluent water as steam plant boiler feed

Description: The radiological aspects of a proposal to recover some of the heat now wasted in cooling water from the Hanford reactors by using the hot water as boiler feed for the steam plants in the 100 Areas are evaluated. The radioactive material in the hot effluent water will contaminate the boiler feed water system, cause additional radiation exposure of personnel, and increase the cost of maintenance and radiation protection, but very little radioactive material will be carried over into the steam sys… more
Date: December 8, 1953
Creator: Clukey, H. V.
Partner: UNT Libraries Government Documents Department
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Radioactive debris from operations Tumbler and Snapper: observations beyond 200 miles from the test site. Part II

Description: The results of the fall-out monitoring program at fixed stations more than 200 miles from the test site following the series of atomic tests in Nevada during the spring of 1952 are shown in a series of maps. Trajectories of debris from the individual bursts are given, together with a discussion of meteorological phenomena associated with the transport of atomic debris.
Date: February 25, 1953
Creator: List, R.J.
Partner: UNT Libraries Government Documents Department
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Unusual incident at Savannah River

Description: On January 12, 1953, an explosion occurred in the Savannah River pilot plant which has been used since November, 1951 by du Pont personnel to train operators and to test equipment for their new Purex production plant. The explosion occurred in an evaporator in which a uranyl nitrate solution containing some organics was being concentrated to a high degree to remove nitric acid. This memorandum reviews the facts surrounding the incident as obtained from the official Preliminary Technical Report'… more
Date: February 5, 1953
Creator: Tomlinson, R.E.
Partner: UNT Libraries Government Documents Department
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Radiation Damage to Organic Ion-Exchange Materials

Description: From abstract: "The stability of polystyrene and phenolic ion-exchange resins to radiation from a Co60 source and from absorbed Ce144-PR144 was investigated. Sulfonated polystyrene cation-exchange resins lost 10 to 20% of their capacity per watt-hour of radiation absorbed per gram of oven-dry resin, while the quaternary amine anion-exchange polystyrene resins lost about 40%. Phenolic cation-exchange resins lost only 1%."
Date: March 16, 1953
Creator: Higgins, I. R.
Partner: UNT Libraries Government Documents Department
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The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor

Description: Technical report covering the technology of hot-pressed beryllium production and its rapid advancement toward the end of 1949. Part I is devoted to corrosion studies made on hot-pressed and vacuum cast extruded metal which was considered representative of production. Part II is concerned with the results of tests made on special cast and hot-pressed beryllium which contained added impurities. [From Introduction]
Date: January 9, 1953
Creator: Reed, James
Partner: UNT Libraries Government Documents Department
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Dynamics of the Supercritical Water Reactor

Description: From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."
Date: February 1, 1953
Creator: Goertzel, Gerald, 1919-; Shapiro, Mathew M. & Soodak, Harry
Partner: UNT Libraries Government Documents Department
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Operating level at C Pile

Description: No Description Available.
Date: February 3, 1953
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Review of oxide facilities: 224-U Bldg.

Description: No Description Available.
Date: February 9, 1953
Creator: Rohrmann, C. A. & Ludlow, J. O.
Partner: UNT Libraries Government Documents Department
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Final report on Production Test 105-528-A -- Alteration of two C-Pile horizontal safety rods for temperature distribution control

Description: Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rod… more
Date: June 11, 1953
Creator: Halliday, A. W.
Partner: UNT Libraries Government Documents Department
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Hydrofluosilicic acid as a cap and can etchant

Description: Aluminum caps and cans are thoroughly cleaned, before being used to can slugs, to insure wetting of the metal surfaces by molten AlSi in the canning pot. An acid bath is used, as part of the cleaning operations to remove surface oxide and other surface films from the metal. Two acid solutions are authorized in the standard operating procedure; a 20% phosphoric acid solution for etching both caps and cans, and a 1% hydrofluosilicic acid solution to be used for caps only. It is desired to determi… more
Date: March 17, 1953
Creator: Dixon, D. S.
Partner: UNT Libraries Government Documents Department
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A Numerical Method for Two-Dimensional Lagrangian Hydrodynamics

Description: Abstract: "A completely Lagrangian scheme for differencing hydrodynamical equations in two dimensions is described. The method conserves mass exactly. The advantages of Lagrangian over Eulerian schemes are briefly mentioned. An appendix gives the generalization to three dimensions."
Date: December 10, 1953
Creator: DeWitt, Bryce S.
Partner: UNT Libraries Government Documents Department
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