Some Recent Observations on the Radiation Behavior of Uranium Silicide Dispersion Fuel PDF Download
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Languages : en
Pages : 20
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Addition of B4C burnable poison results in higher plate swelling in both U3Si2 and U3Si-Al dispersion fuel plates and also decreases the blister threshold temperature of these plates. Prolonged annealing of U3Si2-Al fuel plates produced no blister after 696 hours at 400°C. Blister formation started between 257 hours and 327 hours at 425°C and between 115 hours and 210 hours at 450°C. Operation with breached cladding resulted in pillowing of an U3Si-Al fuel plate due to reaction of the fuel core with coolant water. 4 refs., 10 figs., 2 tabs.
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Category :
Languages : en
Pages : 20
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Addition of B4C burnable poison results in higher plate swelling in both U3Si2 and U3Si-Al dispersion fuel plates and also decreases the blister threshold temperature of these plates. Prolonged annealing of U3Si2-Al fuel plates produced no blister after 696 hours at 400°C. Blister formation started between 257 hours and 327 hours at 425°C and between 115 hours and 210 hours at 450°C. Operation with breached cladding resulted in pillowing of an U3Si-Al fuel plate due to reaction of the fuel core with coolant water. 4 refs., 10 figs., 2 tabs.
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Category : Power resources
Languages : en
Pages : 544
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Category : Engineering test reactors
Languages : en
Pages : 484
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Author: Roger E. Stoller
Publisher: ASTM International
ISBN: 080311477X
Category : Materials
Languages : en
Pages : 1315
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Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization
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Category : Government publications
Languages : en
Pages : 1104
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Category :
Languages : en
Pages :
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SEM observations have shown that irradiation induced interaction of the aluminum cladding with uranium silicide reactor fuels strongly affects both fission gas and fuel swelling behaviors during fuel burn-up. The authors have used ion beam mixing, by 1.5 MeV Kr, to study this phenomena. RBS and the[sup 27]Al(p, [gamma])[sup 28]Si resonance nuclear reaction were used to measure radiation induced mixing of Al into U[sub 3]Si and U[sub 3]Si[sub 2] after irradiation at 300 C. Initially U mixes into the Al layer and Al mixes into the U[sub 3]Si. At a low dose, the Al layer is converted into UAl[sub 4] type compound while near the interface the phase U(Al[sub .93]Si[sub .07])[sub 3] grows. Under irradiation, Al diffuses out of the UAl[sub 4] surface layer, and the lower density ternary, which is stable under irradiation, is the final product. Al mixing into U[sub 3]Si[sub 2] is slower than in U[sub 3]Si, but after high dose irradiation the Al concentration extends much farther into the bulk. In both systems Al mixing and diffusion is controlled by phase formation and growth. The Al mixing rates into the two alloys are similar to that of Al into pure uranium where similar aluminide phases are formed.
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Category : Science
Languages : en
Pages : 530
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Category :
Languages : en
Pages :
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During fabrication of U-7Mo dispersion fuels, exposure to relatively high temperatures affects the final microstructure of a fuel plate before it is inserted into a reactor. One impact of this high temperature exposure is a chemical interaction that can occur between dissimilar materials. For U-7Mo dispersion fuels, the U-7Mo particles will interact to some extent with the Al or Al alloy matrix to produce interaction products. It has been observed that the final irradiation behavior of a fuel plate can depend on the amount of interaction that occurs at the U-7Mo/matrix interface during fabrication, along with the type of phases that develop at this interface. For the case where a U-7Mo dispersion fuel has a Si-containing Al alloy matrix and is rolled at around 500°C, a Si-rich interaction product has been observed to form that can potentially have a positive impact on fuel performance during irradiation. This interaction product can exhibit stable irradiation behavior and it can act as a diffusion barrier to additional U-Mo/matrix interaction during irradiation. However, for U-7Mo dispersion fuels with softer claddings that are rolled at lower temperatures (e.g., near 425°C), a significant interaction layer has not been observed to form. As a result, the bulk of any interaction layer that develops in these fuels happens during irradiation, and the layer that forms may not exhibit as stable a behavior as one that is formed during fabrication. Therefore, it may be beneficial to add a heat treatment step during the fabrication of dispersion fuel plates with softer cladding alloys that will result in the formation of a uniform, Si-rich interaction layer that is a few microns thick around the U-Mo fuel particles. This type of layer would have characteristics like the one that has been observed in dispersion fuel plates with AA6061 cladding that are fabricated at 500°C, which may exhibit increased stability during irradiation. This report discusses the result of annealing experiments that were performed using samples from fuel plates that were fabricated at 425°C that had Alloy 5052 cladding. As part of these experiments, samples with Al-Si matrices that had different Si contents were tested. The samples had Al-2Si, Al-4Si, Al-5Si, or Al-6Si as the matrix alloy. The heat treatment temperatures and times that were investigated were 450°C (4 hours), 475°C (4 hours), and 500°C (2 hours) for all the matrix alloy compositions and 525°C (1 hour) for just the Al-4Si and Al-6Si matrix alloy compositions. The results of these experiments showed that the initial interaction layers that form around the U-7Mo particles during fabrication at 425°C continue to grow in thickness and uniformity during each of the heat treatments, though the composition of the layers remains similar to that observed in the as-fabricated samples. The Al-6Si matrix sample annealed at 450°C for 4 hours and the Al-5Si and Al-6Si matrix samples annealed at 475°C for 4 hours formed fuel/matrix interaction layers most similar to those observed in fuel plates with AA6061 cladding that are fabricated at 500°C.
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Category : Nuclear energy
Languages : en
Pages : 724
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Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
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