Download or read book Rate of Alloying of Uranium Alloys with Stainless Steel written by R. S. Neymark and published by . This book was released on 1960 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Studies of the Aluminum uranium Alloying Reaction written by D. W. Bareis and published by . This book was released on 1955 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: It was found in this investigation that an alloying reaction occurred wherever and whenever clean metallic surfaces of aluminum and uranium were brought into contact within the temperature range of 250OC to 450oC. Anodization of the aluminum surface prevented the alloying reaction. The effects of temperature. aluminum purity, and pressure between the metal surfaces on the alloying reaction were studied qualitatively. The alloying reaction produced UAl3, which appeared to be formed by the diffusion of the uranium through the UAl3 layer. (MM).
Download or read book Effect of Uranium on the Isothermal Transformation and Hardenability of a Low alloy Steel written by K. A. Fowler and published by . This book was released on 1964 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Resume of Uranium Alloy Data written by E. F. Losco and published by . This book was released on 1955 with total page 116 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium written by J. E. Draley and published by . This book was released on 1957 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt: Alloys of uranium with niobium show good corrosion resistance in degassed, distilled water to about 315 degrees C. The alloys must be quenched from the gamma phase in order to have high temperature corrosion resistance. The corrosion resistance is destroyed by over-aging at temperatures as low as 350 degrees C. Of those tried, the alloy with best resistance to thermal aging is the uranium-5% zirconium-1.5% niobium alloy. At 290 degrees C, optimum heat treatment can result in a rate of corrosion of about 6 mg/cm sq/day. Certain moderate aging treatments, e.g., 400 degree C for two hours, result in improved corrosion resistance in the initial stages of corrosion. Alloys containing 3% niobium and small amounts of tin show promise. In addition to aging, the alloys are also sensitive to hydrogen content. Ultimate corrosion failure is believed due to absorption of corrosion product hydrodgen.
Download or read book Corrosion of Uranium 6 Niobium Alloy and Type 304 Stainless Steel Exposed to Type X 0290 Explosive written by and published by . This book was released on 1990 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Resume of Uranium Alloy Data written by D. E. Thomas and published by . This book was released on 1954 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Interdiffusion Between Uranium 5 W o Fissium Alloy and Type 304 Stainless Steel written by C. M. Walter and published by . This book was released on 1964 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: The compatibility of uranium-5 wt.% with Type 304 stainless steel was investigated in the temperature range from 500 to 700 degrees C. Appreciable interdiffusion bands were detected., but only about 5% of the band was into the stainless steel while the bulk of the diffusion was into the fuel.
Download or read book Reactor Core Materials written by and published by . This book was released on 1958 with total page 208 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1070 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Crevice Corrosion of Uranium and Uranium Alloys written by J. W. Frank and published by . This book was released on 1955 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Uranium Metallurgy Uranium corrosion and alloys written by Walter D. Wilkinson and published by . This book was released on 1962 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Aqueous Processes for Dissolution of Uranium molybdenum Alloy Reactor Fuel Elements written by L. M. Ferris and published by . This book was released on 1961 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Metallurgical Studies of Niobium uranium Alloys written by John A. DeMastry and published by . This book was released on 1959 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt: In a continuing program, fabrication characteristics, physical and mechanical properties, and corrosion behavior in air, CO2, NaK, water, and steam were studied for . binary niobium fuel alloys containing 10, 20, 30, 40, 50, and 60 wt.% uranium To evaluate the effects of two major impurities of niobium, oxygen, and zirconium, three niobium base stocks, differing according to the level of these impurities, were used for each alloy. The impurity combinations employed were 600 ppm oxygen and 0.74 wt.% zirconium, 700 ppm oxygen, and 0.17 wt.% zirconium, and 300 ppm oxygen and 0.02 wt.% zirconium, Representative specimens of these alloys retained their hardness up to 900 deg C The 10 and 20 wt.% uraniuin alloys were successfully rorged at 2500 deg F and rolled at 1800 deg F to sheet. Fabrication characteristics of the remaining alloys are under investigation. The 0.2% offset yield strength of the 10 wt.% uranium alloy was 57,200 psi at room temperature and 36,900 psi at 1600 deg F. For the 20 wt.% uranium alloy it was 93,200 psi at room temperature and 71.000 psi at 1600 deg F. The corrosion life of all of the alloys in air at 572 deg F and in CO2 at 600 deg F was superior to that of unalloyed niobium. In 1000- hr exposures to 600 deg F water most of the alloys exhibited corrosion rates only two or three times greater than that of Zircaloy-2. All oi the alloys appear compatible with NaK at 1600 deg F. The impurity combinations employed in the base niobium appeared to have no effect on the corrosion behavior and mechanical properties of the alloys. (auth).
Download or read book Uranium in Steel written by Standard Alloys Company and published by . This book was released on 1921 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Materials written by and published by . This book was released on 1965 with total page 288 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation of U Mo Base Alloys written by M. P. Johnson and published by . This book was released on 1964 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
