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High-Thermal-Conductivity Fin Material for Radiators

Description: This report is the result of a study to develop heat-resistant fin materials possessing a high thermal conductivity for air radiators. Since an economical and commercially feasible product was desired, the investigation was restricted primarily to a study of electroplated copper, clad copper, and copper alloys. Sheet material 0.008 to 0.010 in. thick was evaluated for fabricability and for metallurgical stability and thermal conductivity at 1500°F. From the results of the rests it was concluded that: (1) electroplates were unsatisfactory; (2) clad-copper fins possessing a thermal conductivity of 50% of that of copper are commercially feasible; (3) copper-aluminum alloys possessing a thermal conductivity approaching that of copper at 1500°F are possible. Service tests of clad copper and the copper-aluminum alloys indicate that the choice of materials will be dictated by the requirements of the radiator, since each presents some unique problems.
Date: January 24, 1957
Creator: Inouye, H.
Partner: UNT Libraries Government Documents Department
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A Fluoride Fuel In-Pile Loop Experiment

Description: An inconel loop circulating fluoride fuel (62 1/2 make [unintelligible] NaF, 12 1/2 make [unintelligible] ZrF4, 25 make [unintelligible] UF4, 92 [unintelligible] enriched) was operated at 1485°F with a temperature difference of about 35°F in the Low Intensity Test Reactor for 645 hr. For 475 hr of this time the reactor was at full power, and fission power generation in the loop was 2.7 kw, with a max length power density of 0.4 kw/cc. The total volume of fuel was 1290 cc (5.o kg [unintelligible] and the the flow through the irradiated section was 8.6 fps (Reynolds number 5500). The loop has been disassembled and has been examined by chemical and metallographic analyses. Ne acceleration of corrosion of decomposition of fuel by irradiation was noted, although deposition of fission-product ruthenium was absorbed. Ne mass transfer of Inconel was formed, and the corrosive [unintelligible] was general and relatively light. The average corrosive generation, in the usual form of subsurface yields, was 0.5 [unintelligible], the maximum penetration was 2 to 3 miles.
Date: January 29, 1957
Creator: Sisman, Q; Brundage, W. E.; Parkinson, W. W.; Boumann, C. D.; Correll, R. M; Morgen, J. G. et al.
Partner: UNT Libraries Government Documents Department
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A laboratory Ivestigation of the Fluorination of Crude Uranium Tertrafluoride

Description: Ore concentrates have been converted directly to crude uranium tetrafluoride by hydrogen reduction and hydrofluorination in fluidized-bed reactors. Small-scale laboratory experiments demonstrated that this process can be extended to the production of crude uranium hexafluoride through fluorination of the uranium tetrafluoride in a fluidized bed. The satisfactory temperature range for the reaction lies between 300°C and 600°C. At 450°C the fluorine utilization is between 50 and 80 per cent. With excess fluorine, over 99 per cent of the uranium is volatilized from the solid material. The fluidization characteristics of certain materials are improved by the addition of an inert solid diluent to the bed.
Date: December 1957
Creator: Sandus, O. & Steunenberg, R. K.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report July, August, and September, 1957

Description: Development work continued on a fused salt process for the recovery of uranium from zirconium-matrix fuel alloys. The fuel is dissolved in a sodium fluoride-zirconium fluoride melt at 600°C by hydrogen fluoride sparging. The melt is then sparged with fluorine gas which volatilizes the dissolved uranium as the hexafluoride. The final decontamination and purification of the uranium hexafluoride are accomplished by fractional distillation. The testing of graphite as a container material for the hydrofluorination step was continued. Additional thermal cycling experiments were performed, using a helium sparge in equimolar sodium fluoride-zirconium fluoride melt at 600°C. The extent of penetration of the fused salt into the graphite was determined. No mechanical degradation was present. Dimensional change data were also obtained for graphite vessels in which the fused salt was sparged with hydrogen fluoride.
Date: December 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report for January, February, and March 1957

Description: A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.
Date: July 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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A Coated Cast Iron Crucible for use with Eutectic Al-Si Alloy in the Temperature Range 595°-650°C

Description: The feasibility of the coated metal crucible as a container for eutectic Al-Si alloy has been proven by test. Small, enamel-coated cast iron pots has been proven by test. Small, enamel-coated cast iron pots have successfully withstood the chemically aggressive Al-Si alloy and the adverse influence of an oxidizing atmosphere for a period of 3 months at 725°C. A similarly coated castiron crucible containing 450 pounds of eutectic Al-Si alloy was successfully tested for 144 days in a jacketing operation conducted at 595°-650°C. Under the same conditions, the normal service life of clay-bonded graphite and silicon carbide crucibles rarely exceeds 45 days. The coating material is a commercially available enamel capable of withstanding temperatures up to 790°C (1450°F). It is readily applied to the surface of a variety of ferrous metals and alloys; however, best results are obtained with alloys low in chromium and nickel which also have a low thermal expansion coefficient.
Date: November 1957
Creator: Yaggee, F. L.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1956

Description: A final series of runs was made in a four-inch continuous-flow mixing chamber to study the transfer of isobutanol into water and nitrobenzene into ethylene glycol. Satisfactory techniques were developed to provide for the rapid analysis of these systems. In addition, a light-scattering correlation was prepared to provide a measure of the interfacial area of the yellow-colored nitrobenzene-ethylene glycol mixtures.
Date: March 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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An Abrasive Cutoff Machine for Metallurgical Research on Radioactive Materials

Description: An abrasive cutoff machine design, based upon a previous model, (1) was undertaken to provide for the sampling of radioactive material. the design objective was; first, to provide samples for metallographic examination, second, to provide samples for physical and mechanical property testing, and, third, to meet the following design requirements: 1. Remote operation. 2. Airborne contamination control. 3. Radioactive waste collection. 4. Remote maintenance.
Date: January 5, 1957
Creator: Boyd, C. L.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on the Stratigraphy of the Park City and Phosphoria Formations and an Analysis of the Distribution of Phosphate in Utah

Description: "The Purpose of this paper is to present a preliminary discussion of the stratigraphy of the park city and phosphoric formations with special emphasis on the phosphatic parts and to discuss the distribution of phosphate in Utah. The Mississippian deposits are discussed only briefly because of the lack of new data concerning them"
Date: May 1957
Creator: Cheney, T. M.
Partner: UNT Libraries Government Documents Department
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Location of uranium occurrences in southcentral Wyoming and northwestern Colorado

Description: "The principal uranium deposits in southcentral Wyoming and north-western Colorado are located in or at the margins of broad Tertiary basins. Interesting and possibly commercially significant occurrences are found in other Tertiary and older rocks at widely separated locations within this region. The six maps accompanying this report give the location, name, and ownership of the mines and occurrences from which samples assaying greater than 0.10% U3O8 have been collected. Claim names, location, and ownership are also given for occurrences outside the map areas."
Date: February 1957
Creator: Bromley, Charles P.
Partner: UNT Libraries Government Documents Department
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A Study of Uranium Deposits in the Copper Mountain Area: Fremont and Hot Springs Counties, Wyoming

Description: Report documenting a study of the Copper Mountain area to "evaluate the potential uranium production to determine, if possible, the origin and conditions of deposition of the uranium; and suggest possible guides to prospecting in this and geologically similar areas. All known radioactive deposits were examined and samples were collected for special studies and for assay of uranium content" (p. 5).
Date: July 1957
Creator: Loomis, Tom H. W. & Marks, Lawrence Y.
Location: None
Partner: UNT Libraries Government Documents Department
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An Analysis of Carry Transmission in Computer Addition

Description: The following report analyzes carry transformation circuits and their value when approaching the general problem of carry transmission in computer addition.
Date: September 1957
Creator: Campbell, Sullivan G. & Rosser, Gordon H.
Partner: UNT Libraries Government Documents Department
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Reconnaissance for uranium in northern Texas and southern Oklahoma

Description: A report regarding reconnaissance for Uranium in Northern Texas and Southern Oklahoma. This report concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.
Date: August 1957
Creator: McKay, E. J.
Partner: UNT Libraries Government Documents Department
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Economic Study of the San Rafael River Desert Mining District Emery and Grand Counties, Utah

Description: Report documenting a geologic study of the San Rafael River Desert Mining District, including background describing the stratigraphy and geologic history, and the economic geology study containing more extensive descriptions of the area's mineralogy and uranium ores, including a description of mining and impacts.
Date: March 1957
Creator: Young, Robert G. (Robert Glen), 1923-2011; Million, I. & Hausen, Donald M.
Location: None
Partner: UNT Libraries Government Documents Department
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