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Segregation in Arc-Melted Uranium-Niobium Alloys

Description: Report discussing a study aimed at pinpointing the cause of banding segregation in arc-melted uranium-niobium alloys and suggesting possible methods for eliminating banding.
Date: August 28, 1957
Creator: Dickerson, Ronald F.; Foster, Ellis L. & Chubb, Walston
Partner: UNT Libraries Government Documents Department

Development of Methods for End Capping PWR Fuel Elements

Description: The following report discusses the development of methods for sealing the ends of metallic-cored fuel rods.
Date: December 28, 1955
Creator: Vagi, J. J. & Martin, D. C.
Partner: UNT Libraries Government Documents Department

Creep Strength of Uranium Alloys at 1500 and 1800 F

Description: Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates were obtained in composites of 90 wt % molybdenum-10 wt % UO2 by a stress of 12,000 psi."
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
Partner: UNT Libraries Government Documents Department

The Stability and Existence Range of the Zirconium-Uranium Epsilon Phase

Description: Report discussing studies regarding properties of the zirconium-uranium epsilon phase related to stability and existence range. Data showing this phase's thermodynamic stability is presented as well as the zirconium-uranium constitutional diagram. Oxygen and nitrogen effects on zirconium-uranium alloys and epsilon-phase alloys is included as well as ternary zirconium-uranium-oxygen diagrams.
Date: May 28, 1956
Creator: Rough, Frank A.; Austin, Alfred E.; Bauer, Arthur A. & Doig, J. Robert
Partner: UNT Libraries Government Documents Department

Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures

Description: Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mistakes of UF4 containing from 10 to 40 w/o UO2."
Date: June 28, 1956
Creator: Ewing, Robert A. & Bearse, Arthur E.
Partner: UNT Libraries Government Documents Department