Irradiation of an Aluminum Alloy-clad, Aluminum-uranium Alloy-fueled Plate PDF Download
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Author: A. P. Gavin Publisher: ISBN: Category : Irradiation Languages : en Pages : 52
Book Description
Irradiation tests of an aluminum-alloy-clad aluminum -uranium alloy- fueled plate were discontinued due to cladding failure after a maximum burnup of 58%. Cause of the failure was local corrosion of the aluminum alloy. Swelling was observed which was attributed to the combination of high burnup and high fuel temperatures.
Author: A. P. Gavin Publisher: ISBN: Category : Irradiation Languages : en Pages : 52
Book Description
Irradiation tests of an aluminum-alloy-clad aluminum -uranium alloy- fueled plate were discontinued due to cladding failure after a maximum burnup of 58%. Cause of the failure was local corrosion of the aluminum alloy. Swelling was observed which was attributed to the combination of high burnup and high fuel temperatures.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
To be published in TID-7642, Proceedings of the Research Reactors Fuel Element Conference held in Gatlinburg, Tenn., Sept. 17-19, 1962. Irradiation experiments have been made to determine the irradiation temperature and burnup limits ior X8001 aluminum alloy-clad Al-17.5 wt % U-2 wt % Ni-0.5 wt % Fe alloy silicon-bonded plates of the type developed ior the SL-1 reactor. The irradiations were conducted on prototype SL-1 plates both in MTR capsules and in the ANL-2 High Pressure Water Loop in the MTR. The loop experiments were conducted under local boiling conditions in water at 215 deg C (420 deg F) flowing at 12 ft/sec. One of the plates being irradiated in the loop developed a clad defect after a period of operation in high pH water. At the time of clad penetration the plate had achieved a burnup of 58 percent of the uranium (1.3 percent of total fuel alloy atoms). No catastrophic corrosion of the fuel alloy or extensive fission product release occurred when the plate was irradiated with the defect. Because of heavy scale deposition on the loop specimens fuel alloy temperatures were calculated to be as high as 560 deg C (1040 deg F). Fuel swelling occurred above temperatures near 450 deg C (840 deg F). The silicon bonding technique appeared to be highly effective in maintaining sound metallurgical bonds between fuel and cladding. (auth).
Author: A. P. Gavin Publisher: ISBN: Category : Alloys Languages : en Pages : 50
Book Description
The specimen performed satisfactorily in spite of several factors which made conditions more severe than those expected to exist in a reactor fueled with this type of element.
Author: L. A. Neimark Publisher: ISBN: Category : Nuclear fuel elements Languages : en Pages : 42
Book Description
Specimens consisting of thorium oxide-uranium oxide pellets lead-bonded to extruded Al-1wt.% Ni alloy cladding were irradiated to maximum burnups of 33,200 MWd/T of oxide and to peak heat ratings. The specimens were BORAX-V fuel plates. The thorium oxide-uranium oxide solid solutions were formed by air-firing cold-pressed mixtures of thorium oxide and U3O8 to a final oxygen-to-metal atom ratio of about 2.05 to 1. Fuel compositions irradiated were 6.36, 12.7, and 25.6 wt.% UO2 in ThO2. Two specimen failures were attributed to fuel thermal expansion in areas of thin-walled cladding. The hyperstoichiometry of the fuel with respect to oxygen was believed to have caused a lower fuel thermal conductivity and abnormally large amounts of recrystallization, grain growth, and fission gas release. Fission gas release ranged from 4.6 to 82.3% of the theoretical gas generated.
Author: A. P. Gavin
Author: A. P. Gavin
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Author: A. P. Gavin
Author: R. J. Beaver
Author: S. Priceman
Author: R. M. Crawford
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Author: L. A. Neimark
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