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Author : W. W. Schulz
Publisher :
ISBN 13 :
Total Pages : 84 pages
Book Rating : 4.3/5 (91 download)
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 REPROCESSING OF LOW-ENRICHMENT URANIUM-MOLYBDENUM ALLOY FUELS. written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Procedures for the dissolution of U-Mo alloy fuels to prepare feed solutions for low-acid (Redox) type solvent extraction processing are presented. U-Mo alloys can be dissolved in boiling ferric nitrate--ritric acid solutions to higher terminal urarium concentrations and lower terminal acidities without precipitation of uranyl molybdate than in nitric acid alone. Anion resin exchange studies indicate the presence of negatively charged iron-molybdenum complex ions in the solutions. The U-Mo alloys also dissolve more rapidly in ferric nitrate--nitnic acid solutions than in nitric acid alone; dissolution rate data are given. Curves delineating free acid, uranium, snd iron (III) concentrations within which solutions stable towards solids formation can be prepared from U-3 wt.% Mo and U-10 wt.% Mo alloys are presented. Stability during prolonged storage of uranium--molybdenum-ferric nitrate--nitric acid solutions is discussed. Data on the oxidation of plutonium in these solutions and on further neutralization of the solutions are presented. Fission product decontamination and product recovery obtained in solvent extraction studies simulating the Redox process are discussed. (auth).
Author : Wallace W. Schulz
Publisher :
ISBN 13 :
Total Pages : 21 pages
Book Rating : 4.:/5 (68 download)
Download or read book Reprocessing of Uranium-molybdenum Alloy Reactor Fuels written by Wallace W. Schulz and published by . This book was released on 1960 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W. W. Schulz
Publisher :
ISBN 13 :
Total Pages : 42 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reprocessing Uranium-molybdenum Alloy Fuels written by W. W. Schulz and published by . This book was released on 1960 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W W. Schulz
Publisher :
ISBN 13 :
Total Pages : 32 pages
Book Rating : 4.:/5 (219 download)
Download or read book Reprocessing Uranium-molybdenum Alloy Fuels written by W W. Schulz and published by . This book was released on 1960 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book REPROCESSING URANIUM-MOLYBDENUM ALLOY FUELS-DISSOLUTION IN CONCENTRATED NITRIC ACID. written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO3 solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO3. Plutonium and uranium values in washed precipitates can be recovered by successive treatment of solid residues with caustic and nitric acid. Removal of nitric acid from uranium-molybdenum alloy dissolver solutions by boil-down procedures and by reaction with formaldehyde is discussed. Solutions obtained after removal of nitric acid constitute satisfactory low-acid Redox process feedstocks. (auth).
Author : L. M. Ferris
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 (91 download)
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:
Author : P. Chiotti
Publisher :
ISBN 13 :
Total Pages : 772 pages
Book Rating : 4.3/5 (91 download)
Download or read book Symposium on Reprocessing of Nuclear Fuels written by P. Chiotti and published by . This book was released on 1969 with total page 772 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : National Research Council
Publisher : National Academies Press
ISBN 13 : 0309130395
Total Pages : 220 pages
Book Rating : 4.3/5 (91 download)
Download or read book Medical Isotope Production Without Highly Enriched Uranium written by National Research Council and published by National Academies Press. This book was released on 2009-06-27 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.
Author : J. Guon
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 (91 download)
Download or read book Low Decontamination Reprocessing Studies on Irradiated Uranium Oxide Reactor Fuel written by J. Guon and published by . This book was released on 1962 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Levi D. Gardner
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (97 download)
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.
Author : T. A. Gens
Publisher :
ISBN 13 :
Total Pages : 28 pages
Book Rating : 4.3/5 (91 download)
Download or read book An Oxyhydrochlorination Process for Preparing Uranium-molybdenum Reactor Fuels for Solvent Extraction written by T. A. Gens and published by . This book was released on 1961 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : L. J. Colby
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 (91 download)
Download or read book Comparative Fuel Cycle Evaluations Low Decontamination Pyroprocessing Vs. Aqueous Reprocessing written by L. J. Colby and published by . This book was released on 1963 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reprocessing RERTR Fuels written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Reduced Enrichment Research and Test Reactor Program is one element of the United States Government's nonproliferation effort. High density, low enrichment aluminum-clad dispersed uranium compound fuels may be substituted for the highly enriched aluminum-clad aluminum-uranium alloy fuels now in use. Savannah River Laboratory has performed studies which demonstrate reprocessability of spent RERTR fuels at Savannah River Plant. Results of dissolution and feed preparation tests with both unirradiated and irradiated (up to approximately 90% burnup) fuels are presented. 13 references, 2 figures, 4 tables.
Author : M. P. Johnson
Publisher :
ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.3/5 (91 download)
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
Author :
Publisher :
ISBN 13 :
Total Pages : 726 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reactor Fuel Processing written by and published by . This book was released on 1963 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 721 pages
Book Rating : 4.:/5 (487 download)
Download or read book English-Chinese Telecommunication Dictionary written by and published by . This book was released on 1974 with total page 721 pages. Available in PDF, EPUB and Kindle. Book excerpt:
