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A study was made of the preparation of a uranium - 10 w/O niobium alloy by the bomb reduction of a suitable form of niobium and uranium tetrafluoride with calcium. A compound with a probable formula of Na2NbOF5 proved to be most satisfactory as the source of niobium. High yields and good metal-slag separations were obtained. Chemical analysis and density determinations showed the composition to be 10 ℗± 0.5 w/o niobium. Fifteen pounds of alloy were melted in BeO and cast into a graphite mold.
A satisfactory procedure is described for the analysis of uranium-niobium alloys containing up to 25% niobium. It is based on the separation of the niobium from uranium by dissolving the cupferron complex of the former element into chloroform. After the evaporation of the solvent from the combined organic extracts, the niobium is ignited to the pentoxide. The uranium is afterwards precipitated from the remaining aqueous solution by the addition of ammonium hydroxide after the wet oxidation of organic matter. Absorptiometric procedures are included for the determination of the small amounts of uranium co-extracted with the niobium and the trace amounts of unextracted niobium. (auth).
Uranium-niobium alloys play an important role in the nation's nuclear stockpile. It is possible to chemically quantify this alloy at a micron scale by using a technique know as wavelength dispersive spectroscopy. This report documents how this technique was used and how it is possible to reproduce measurements of this type. Discussion regarding the accuracy and precision of the measurements, the development of standards, and the comparison of different ways to model the matrices are all presented.
A study was made of the methods for preparing, processing, and heat treating uranium-2.25 wt percent niobium alloys. The rolling technique is critical, but the alloy responds to conventional solution treatment, water quenching, and aging to provide high strength with good ductility. Data on tensile tests and Charpy tests as functions of the temperature have been obtained. Elastic moduli, density, coefficient of thermal expansion, and differential thermal analysis data have also been determined. (auth).
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, while the thermal-expansion characteristics are essentially unaffected. Recrystallization temperatures for 90% cold-reduced niobium-4.38, -14.3, -20, -25.0, and -30 wt.% uranium alloys are 2300, 2300, 2400, 2300, and 2200 deg F, respectively. No appreciable effect of oxygen contents ranging from 100 to 1000 ppm was observed on the composition limits of the gamma immiscibility gap in the niobium-- uranium system. (auth).