Download Free A Study Of The Mechanical Properties Of Heat Treated Uranium M Nb Zr Alloy Book in PDF and EPUB Free Download. You can read online A Study Of The Mechanical Properties Of Heat Treated Uranium M Nb Zr Alloy and write the review.

A study was made of a uranium-2% Mo-2%Zr-2%Nb-0.5%Ti alloy in the rolled and forged conditions. It was found that, in the asworked condition, this alloy possessed little or no ductility. However, in the solution-treated and aged condition, it did possess a measurable amount (1 to 3 percent elongation) of ductility. (Author).
Argonne National Lab. Results are summarized from irradiation and corrosion tests on alloys of U--Pu, U--Nb-Sn, and U- Zr-Nb, and U-- Si systems. Armour Research Foundation. Studies of the transformation kinetics of Ubase alloys have been completed, and results are summarized. TTT diagrams are presented for 2 Nb--U alloys. Battelle Memorial Inst. Phase studies, heat treatment studies, and preparation of U-- Zr alloys are described. The study of the properties and preparation of various U alloys for use as fuel elements are continuing. Techniques for melting and casting Al--U alloys and for melting U-- Zr alloys are being developed. Hanford Atomic Products Operation. Results of metallographic and phase studies on U-- Th alloys are reported. The corrosion resistance of several Th--U-- Zr alloys has been studied. National Bureau of Standards. The preparation and phase relations of alloys of U with the platinum metals are being studied. North American Aviation, Incorporated The feasibility of fabricating specific U alloys for fuel elements on a semi-production scale is being investigated. Nuclear Metals, Incorporated Studies of the thermal properties of U- -Nb--Zr alloys and of the corrosion of U-- Si systems are reported. Fabrication behavior and microstructures in cast, extruded, and heat treated U alloys are being examined. Sylvania Electric Products, Incorporated Data are presented on the mechanical properties and dimensional stability under thermal cycling of various powder metallurgy binary U alloys. Corrosion rates in water and densities are reported of some powder metallurgy Si-- U systems. Westinghouse Atomic Power Div. The changes in dimensions, density, electrical resistivity, and hardness of irradiated U--Mo and U--Nb alloys are tabulated. The effects of irradiating prototype fuel rods of U and U--Zr alloy are reported. (W.L.H.).
The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed.
NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.
The addition of alloying elements to base alloys of Th containing 5 and 10 wt% U was investigated with regard to alloy structures and elevated- temperature mechanical properties. The alloys developed possess elevated temperature tensile and stress-rupture strengths of essentially twice those associated with binary Th-5 and 10 wt% U alloys at 60O to 800 deg C. The greater strength of these alloys should resuit in improved resistance to radiation induced swelling at high temperatures. Noticeable improvement in elevated-temperature mechanical properties resulted from the addition of 2 and 5 wt% Zr to the Th-5 and Th-10 wt% U base alloys. Zr was found to be the most effective additive in improving elevated-temperature mechanical properties, although significant improvement was noted with additions of Nb, Mo, C, Al, and Be. Both solidsolution strengthening and dispersion strengthening of the Th --U base alloys were encountered. It was found that a fine intragranular distribution of the secondary U phase improved the mechanical properties of the alloys studied. Structures with optimum properties were produced by careful control of the arc-melting procedure and by solution heat treating at 1350 deg C followed by aging at 850 deg C. Preliminary testing was performed to determine the elevatedtemperature mechanical properties of Th metal and of the Th --U base alloys. Irradiation specimens of the most promising alloys were prepared. These specimens were encapsulated and are ready for irradiation testing at 800 deg C and for subjection to burnups of 10,000, 20,000 and 30,000 Mwd/ ton. (auth).