Effects of Irradiation on Powder Compacts of Uranium and Some Uranium-base Alloys PDF Download
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Author: J. H. Kittel Publisher: ISBN: Category : Irradiation Languages : en Pages : 48
Book Description
Results are given from irradiation experiments on powder compacts prepared from uranium, uranium hydride, and a number of uranium alloys. The methods by which the compacts were prepared included end-pressing, side-pressing, hot-rolling, and hot-swaging. When subjected to irradiation, the uranium compacts invariably shortened in the pressing direction, whereas the compacts prepared from uranium hydride elongated in the pressing direction. The alloy compacts elongated in the direction of pressing, rolling, or swaging. Both the unalloyed and alloyed compacts decreased in density under irradiation, and the rate of density decrease was found to depend strongly on the irradiation temperature.
Author: J. H. Kittel Publisher: ISBN: Category : Irradiation Languages : en Pages : 48
Book Description
Results are given from irradiation experiments on powder compacts prepared from uranium, uranium hydride, and a number of uranium alloys. The methods by which the compacts were prepared included end-pressing, side-pressing, hot-rolling, and hot-swaging. When subjected to irradiation, the uranium compacts invariably shortened in the pressing direction, whereas the compacts prepared from uranium hydride elongated in the pressing direction. The alloy compacts elongated in the direction of pressing, rolling, or swaging. Both the unalloyed and alloyed compacts decreased in density under irradiation, and the rate of density decrease was found to depend strongly on the irradiation temperature.
Author: M. P. Johnson Publisher: ISBN: Category : Molybdenum alloys Languages : en Pages : 38
Book Description
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. H. Kittel
Author: J. H. Kittel
Author: 
Author: J. H. Kittel
Author: A. A. Bauėr
Author: United States Dept. of Commerce. Office of Technical Services
Author: 
Author: M. P. Johnson
Author: Helen C. Friedemann
Author: 
Author: U.S. Atomic Energy Commission