Download or read book Hot Pressing of Low molybdenum uranium Alloys written by G. S. Hanks and published by . This book was released on 1961 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Ultrasonic Hot Pressing of Metals and Ceramics written by William B. Tarpley and published by . This book was released on 1961 with total page 32 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

Download or read book Some Properties of Uranium molybdenum Alloy Fuels for Organic Moderated Reactors written by W. H. Friske and published by . This book was released on 1960 with total page 30 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 1976-06 with total page 1216 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Low Temperature Aqueous Corrosion Behavior of Uranium Molybdenum Alloys written by Levi D. Gardner and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear fuel characterization requires understanding of the various conditions to which materials are exposed in-reactor. One of these important conditions is corrosion, particularly that of fuel constituents. Therefore, corrosion behavior is of special interest and an essential part of nuclear materials characterization efforts. In support of the Office of Material Management and Minimization0́9s Reactor Conversion Program, monolithic uranium-10 wt% molybdenum alloy (UMo) is being investigated as a low enriched uranium alternative to highly enriched uranium dispersion fuel currently used in domestic high performance research reactors. The aqueous corrosion behavior of U-Mo is being examined at Pacific Northwest National Laboratory (PNNL) as part of U-Mo fuel fabrication capability activity. No prior study adequately represents this behavior given the current state of alloy composition and thermomechanical processing methods, and research reactor water chemistry. Two main measurement techniques were employed to evaluate U-Mo corrosion behavior. Low-temperature corrosion rate values were determined by means of U-Mo immersion testing and subsequent mass-loss measurements. The electrochemical behavior of each processing condition was also qualitatively examined using the techniques of corrosion potential and anodic potentiodynamic polarization. Scanning electron microscopy (SEM) and optical metallography (OM) imagery and hardness measurements provided supplemental corrosion analysis in an effort to relate material corrosion behavior to processing. The processing effects investigated as part of this were those of homogenization heat treatment (employed to mitigate the effects of coring in castings) and sub-eutectoid heat treatment, meant to represent additional steps in fabrication (such as hot isostatic pressing) performed at similar temperatures. Immersion mass loss measurements and electrochemical results both showed very little appreciable difference between specimens of different process parameters. Comparative results were presented as linear corrosion rates and temperature-dependent Arrhenius equations, which were then correlated with electrochemical and metallographic findings for each condition under investigation. This thesis was prepared in the monograph style using the ASME reference format.

Download or read book U S Government Research Reports written by and published by . This book was released on 1961 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dimensional Changes Resulting from Alpha beta Thermal Cycling of Uranium and Uranium Alloys written by B. R. Hayward and published by . This book was released on 1956 with total page 38 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 Design and Analysis of a Uranium 3 5 Molybdenum Alloy written by B. L. Hoffman and published by . This book was released on 1961 with total page 154 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reprocessing of Low enrichment Uranium molybdenum Alloy Fuels written by W. W. Schulz and published by . This book was released on 1959 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Extrusion written by and published by ASM International. This book was released on 2006 with total page 603 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Atomic Energy Research Reports for Sale by the U S Department of Commerce Office of Technical Services written by Business and Defense Services Administration and published by . This book was released on 1963 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Power Reactor Technology written by and published by . This book was released on 1957 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Peaceful Uses of Atomic Energy written by and published by . This book was released on 1958 with total page 748 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book List written by and published by . This book was released on 1948 with total page 564 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 1985 with total page 364 pages. Available in PDF, EPUB and Kindle. Book excerpt: