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I. Niobium(IV) Bromide and Pyridine Adducts of the Niobium(IV) Halides

Description: Technical report. From Abstract : "Reaction of NbBr5 and niobium metal in a sealed tube under a temperature gradient from 410° to 350° gave NbBr4 in good yields. However, an increase in the higher temperature from 410° to 450° was sufficient to eliminate NbBr4 as a product and cause deposition of a lower bromide."
Date: September 5, 1962
Creator: McCarley, Robert E. & Torp, Bruce A.
Partner: UNT Libraries Government Documents Department
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The Preparation of TaBr4, TaI4 and Pyridine Adducts of the Tantalum(IV) Halides

Description: Technical report. From Abstract : "The necessary conditions for preparation of TaBr4 and TaI4 by reduction of the pentahalides with tantalum or aluminum metal in a sealed tube under a controlled temperature gradient have been demonstrated."
Date: September 5, 1962
Creator: McCarley, R. E. & Boatman, J. C.
Partner: UNT Libraries Government Documents Department
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Electrical Resistivity of Rare-Earth Alloys

Description: From abstract: "Resistivities of solid solution alloys in the systems Gd-Lu, Tb-Lu, Gd-Er, and Y-Lu were measured from 4.2-320°K to determine the behavior of the resistivity in alloy systems with magnetic phenomena arising from localized magnetic moments. A large contribution to the residual resistivity is caused by the random distribution of these localized moments through the lattice. An analysis of the lattice resistivity of the metals shows large variations across the heavy rare-earth serie… more
Date: June 5, 1962
Creator: Smidt, F. A. & Daane, A. H. (Adrian Hill), 1919-
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

Description: One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Partner: UNT Libraries Government Documents Department
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High Pressure Pump Seal Development

Description: "Test results indicated that graphite is not suitable for seal face material. A program to evaluate various materials and seal face geometries was initiated. A seal run using nucerite-bearium combination was carried on for six hours."
Date: March 5, 1962
Creator: Zanoni, P. J.
Partner: UNT Libraries Government Documents Department
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Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Description: Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II an… more
Date: October 5, 1960
Creator: Paluszkiewicz, S.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

Description: This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
Partner: UNT Libraries Government Documents Department
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A Miniature Mixer Settler

Description: Unit developed at Knolls Atomic Power Laboratory for extraction and overcomes the disadvantages of the batch countercurrent units currently in use.
Date: January 5, 1956
Creator: Alter, H. Ward; Coplan, B. V. & Zebroski, E. L.
Partner: UNT Libraries Government Documents Department
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MTR Technical Branch Quarterly Report for First Quarter - 1954

Description: The following report is a quarterly report for first quarter in 1954 for the Phillips Petroleum Company. During the first quarter of 1954 considerable progress was made on the design, construction and testing required to initiate work on new programs. The result of this is the beginning construction and design on the Reactivity Measurement Facility.
Date: December 5, 1955
Creator: Huffman, J. R.
Partner: UNT Libraries Government Documents Department
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Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Description: Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 … more
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Partner: UNT Libraries Government Documents Department
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Progress Report on Loading of Titanium with Deuterium

Description: Report issued by the University of California Radiation Laboratory discussing an experiment in which a system was designed and built to load titanium with deuterium gas of a high purity. It discusses the results and the parameters affecting the amounts and purity of the absorbed gas.
Date: May 5, 1955
Creator: Ruff, James W.
Partner: UNT Libraries Government Documents Department
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The Development of Fixed Screen Resin-In-Pulp Devices

Description: A resin-in-pulp process was developed using a series of fixed-screen or Winchester cells. Various laboratory and pilot plant models were constructed and tested under simulated plant conditions. The fixed-screen device proved very effective in the recovery of uranium and/or vanadium by a continuous, resin-in-pulp process.
Date: August 5, 1954
Creator: Charles, W. D.; Thorpe, D. F.; Lower, G. W.; Kaufman, David; Schiff, Norman N.; Abrams, Charles S. et al.
Partner: UNT Libraries Government Documents Department
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Removal of Deuterated Boric Acid From Deuterium Oxide Solution by Ion Exchange Resin

Description: Introduction: "Because of the importance of the value of the transport mean free path of thermal neutrons in deuterium oxide, Kash and Woods proposed to redetermine this value in deuterium oxide (99.4 atom-percent deuterium, by an extrapolation method. Kash and Woods thought that the low value of the transport mean free path might be a source of error. This paper relates studies of procedures by which (1) boron material would be dissolved in high content deuterium oxide without adding foreign … more
Date: January 5, 1954
Creator: Silverman, L.
Partner: UNT Libraries Government Documents Department
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Neutron Total Cross Section for Bismuth and Uranium Between 45 and 160 Mev

Description: "Neutron total cross sections for bismuth and uranium have been measured in a good geometry transmission experiment, using a time-of-flight instrumentation. The source of neutrons was the stripped deuteron beam of the 184-inch synchrocyclotron. The results are shown in Fig. 1. Uncertainties are shown in terms of standard deviations, due to counting statistics only, and to energy channel width."
Date: August 5, 1953
Creator: Linlor, William I., 1915- & Ragent, Boris
Partner: UNT Libraries Government Documents Department
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