Material Properties Of Unirradiated Uranium Molybdenum U Mo Fuel For Research Reactors

Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9789201157201
Total Pages : 144 pages
Book Rating : 4.07/5 ( download)

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Download or read book Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2020-10-12 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research

Author : M. P. Johnson
Publisher :
ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.64/5 ( download)

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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 : W. H. Friske
Publisher :
ISBN 13 :
Total Pages : 30 pages
Book Rating : 4.16/5 ( download)

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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:

Author : William C. Dietrich
Publisher :
ISBN 13 :
Total Pages : 32 pages
Book Rating : 4.46/5 ( download)

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Download or read book The Determination of Molybdenum in Uranium-molybdenum Alloys by Monochromatic X-ray Absorption written by William C. Dietrich and published by . This book was released on 1957 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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ISBN 13 :
Total Pages : pages
Book Rating : 4.91/5 ( download)

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Download or read book Maternidad no deseada! written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Tanja Huber
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.00/5 ( download)

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Download or read book Thermal Conductivity of High-density Uranium-molybdenum Fuels for Research Reactors written by Tanja Huber and published by . This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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ISBN 13 :
Total Pages : pages
Book Rating : 4.06/5 ( download)

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Download or read book Thermophysical Properties of U-10MO Alloy written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report provides an overview of thermophysical properties of unirradiated uranium alloyed with ten weight percent molybdenum (U 10Mo), with particular focus on those material properties needed for modeling of new fuels for HPRRs (High Performance Research Reactors). The report contains both historical data available in the literature on U-10Mo, as well as more recent results conducted by the Global Threat Reduction Initiative fuel development program. The main use of the report is intended as a standard U-10Mo alloy properties reference for reactor models and simulations.

Author :
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ISBN 13 :
Total Pages : pages
Book Rating : 4.67/5 ( download)

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Download or read book Compilation of Uranium-10 W/o Molybdenum Fuels Alloy Properties. Technical Memorandum written by and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The mechanical and physical properties of U --10 wt.% Mo before and after irradiation have been studied. The pre-irradiation properties and some of the post-irradiation physical properties are presented in graphical and tabular form. (J.S.R.).

Author :
Publisher :
ISBN 13 :
Total Pages : 9 pages
Book Rating : 4.95/5 ( download)

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Download or read book Qualification of Uranium-molybdenum Alloy Fuel -- Conclusions of an International Workshop written by and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thirty-one participants representing 21 reactors, fuel developers, fuel fabricators, and fuel reprocessors in 11 countries discussed the requirements for qualification of U-MO alloy fuel at a workshop held at Argonne National Laboratory on January 17--18, 2000. Consensus was reached that the qualification plans of the US RERTR program and the French U-Mo fuel development program are valid. The items to be addressed during qualification are summarized in the paper.

Author : Jason L. Schulthess
Publisher :
ISBN 13 : 9781085583084
Total Pages : 174 pages
Book Rating : 4.82/5 ( download)

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Download or read book Degradation of Mechanical Properties of U-Mo Alloy from the Un-irradiated to Irradiated State written by Jason L. Schulthess and published by . This book was released on 2018 with total page 174 pages. Available in PDF, EPUB and Kindle. Book excerpt: Studies were conducted to establish the mechanical properties of uranium 10 wt.% molybdenum (U-10Mo) in both the un-irradiated condition and after neutron irradiation. In the un-irradiated condition, mechanical properties were obtained for various temperatures and after the alloy had been wrought processed by rolling into four different rolling conditions. The irradiated mechanical properties were obtained at various fission densities and then the degradation of the mechanical properties from the un-irradiated to irradiated condition evaluated and a correlation with porosity developed. The mechanical properties obtained of the un-irradiated material differed from that previously published in the literature, which was expected due to the differences in thermomechanical processing conditions between the materials evaluated. The mechanical properties degraded as fission density increased as expected, and correlate to the increase of porosity that develops with increasing fission density.