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Author : W. H. Friske
Publisher : Unknown
Page : 30 pages
File Size : 42,9 Mb
Release : 1960
Category : Molybdenum alloys
ISBN : UOM:39015095003516
Author : Leonard E. Link
Publisher : Unknown
Page : 634 pages
File Size : 43,7 Mb
Release : 1964
Category : Nuclear reactors
ISBN : STANFORD:36105030142702
Author : Anonim
Publisher : Unknown
Page : 310 pages
File Size : 54,9 Mb
Release : 1960
Category : Organic cooled reactors
ISBN : UOM:39015095004464
Author : Anonim
Publisher : Unknown
Page : 1094 pages
File Size : 45,6 Mb
Release : 1961
Category : Nuclear reactors
ISBN : UOM:39015019466955
Author : Anonim
Publisher : Unknown
Page : 940 pages
File Size : 54,7 Mb
Release : 1958
Category : Nuclear reactors
ISBN : UOM:39015023318176
Author : Anonim
Publisher : Unknown
Page : 1080 pages
File Size : 45,8 Mb
Release : 1973
Category : Nuclear energy
ISBN : PSU:000047759596
Author : Anonim
Publisher : Unknown
Page : 950 pages
File Size : 42,6 Mb
Release : 1960
Category : Science
ISBN : OSU:32435022153621
Author : Business and Defense Services Administration
Publisher : Unknown
Page : 68 pages
File Size : 48,8 Mb
Release : 1963
Category : Electronic
ISBN : STANFORD:36105133447230
Author : M. P. Johnson,W. A. Holland
Publisher : Unknown
Page : 38 pages
File Size : 50,6 Mb
Release : 1964
Category : Molybdenum alloys
ISBN : UOM:39015095005164
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 : J. Kroehler
Publisher : Unknown
Page : 48 pages
File Size : 40,8 Mb
Release : 1960
Category : Nuclear fuel elements
ISBN : UOM:39015095003797
Author : Anonim
Publisher : Unknown
Page : 564 pages
File Size : 46,9 Mb
Release : 1948
Category : Nuclear energy
ISBN : IND:30000113325710
Author : Bureau of National Affairs (Arlington, Va.)
Publisher : Unknown
Page : 1830 pages
File Size : 53,9 Mb
Release : 1955
Category : Nuclear energy
ISBN : UOM:39015001339624
Author : International Atomic Energy Agency
Publisher : Unknown
Page : 144 pages
File Size : 43,7 Mb
Release : 2020-10-12
Category : Technology & Engineering
ISBN : 9201157207
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 : Anonim
Publisher : Unknown
Page : 770 pages
File Size : 50,8 Mb
Release : 1959
Category : Nuclear engineering
ISBN : UCAL:B3155103
Author : Anonim
Publisher : Unknown
Page : 1370 pages
File Size : 41,8 Mb
Release : 1967
Category : Aeronautics
ISBN : UFL:31262082068916