Download or read book Variables which Influence the Stress corrosion Cracking of Uranium 7 5 Niobium 2 5 Zirconium Alloy written by and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Survey of Factors which Influence Stress Corrosion Crack Initiation in Several Uranium Base Alloys written by L. L. Stephenson and published by . This book was released on 1970 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1972 with total page 1056 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 1975-04 with total page 1082 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1984 with total page 1076 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Stress corrosion Cracking Behavior of Uranium 7 5 Nb 2 5 Zr written by Chinhong Chen and published by . This book was released on 1974 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Corrosion Properties of Zirconium base Fuel Alloys written by Sam Kass and published by . This book was released on 1956 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Government Reports Annual Index written by and published by . This book was released on 1975 with total page 882 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Corrosion Abstracts written by and published by . This book was released on 1975 with total page 550 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Stress Corrosion Cracking of Uranium niobium Alloys written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The stress corrosion cracking behavior of U-21/4, 41/2, 6 and 8 wt % Nb alloys was evaluated in laboratory air and in aqueous Cl− solutions. Thresholds for crack propagation were obtained in these environments. The data showed that Cl− solutions are more deleterious than air environments. Tests were also conducted in pure gases to identify the species in the air responsible for cracking. These data showed the primary stress corrodent is water vapor for the most reactive alloy, U-21/4% Nb, while O2 is primarily responsible for cracking in the more corrosion resistant alloys, U-6 and 8% Nb. The 41/2% alloy was found to be susceptible in both H2O and O2 environments.

Download or read book INIS Atomindex written by and published by . This book was released on 1987 with total page 870 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 High temperature Water and Steam corrosion Behavior of Zirconium uranium Alloys written by Stanley Kass and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Bibliographic Survey of Corrosion written by National Association of Corrosion Engineers and published by . This book was released on 1971 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt: A compilation of corrosion abstracts.

Download or read book Review and Correlation of In pile Zircaloy 2 Corrosion Data and a Model for the Effect of Irradiation written by Glenn Herbert Jenks and published by . This book was released on 1961 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Investigation of Variables That Influence Corrosion of Zirconium Alloys During Irradiation written by VF. Urbanic and published by . This book was released on 1991 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The in-reactor corrosion of Zircaloy-2 and Zr-2.5Nb pressure tube materials is being studied by exposing small specimens in water-cooled loops in the NRU research reactor. Experiments are designed to investigate the effects of fast-neutron irradiation, water chemistry, temperature, and pre-oxidation on the corrosion behaviour. Preliminary results show that inreactor corrosion rates of both alloys increase with increasing concentrations of dissolved oxygen in the water. In the absence of irradiation, only Zr-2.5Nb is sensitive to its presence. Excursions to oxidizing (?300 (?g/kg oxygen) water chemistry in nominally low oxygen tests are seen to induce high oxidation rates for both Zircaloy-2 and Zr-2.5Nb during irradiation. The consequences of oxygen excursions are less pronounced on material prefilmed in 673 K steam. The oxides formed in different chemistry regimes are characterized using scanning electron microscopy and capacitance techniques.