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Author: Publisher: ISBN: Category : Languages : en Pages : 76
Book Description
This report discusses Zircaloy-2 clad uranium and uranium-2 weight percent zirconium fuel tubes which were irradiated to 3200 MWD/T in a high temperature water cooled loop. The outer clad of one tube split due to swelling of the uranium. Postirradiation examination of the fuel cores included metallography, electron microscopy, density determinations, dimensional measurements, and radiochemical burn-up analysis.
Author: Publisher: ISBN: Category : Languages : en Pages : 76
Book Description
This report discusses Zircaloy-2 clad uranium and uranium-2 weight percent zirconium fuel tubes which were irradiated to 3200 MWD/T in a high temperature water cooled loop. The outer clad of one tube split due to swelling of the uranium. Postirradiation examination of the fuel cores included metallography, electron microscopy, density determinations, dimensional measurements, and radiochemical burn-up analysis.
Author: Publisher: ISBN: Category : Languages : en Pages : 6
Book Description
The objectives of this production test detailed in this report is to evaluate the behavior during irradiation of tubular fuel elements with hot-headed end closures. With natural uranium twenty-inch tube- and-tube elements will be irradiated to a goal of 2500 MWD/T in the KER loops. The inner tubes will be closed by the hot-heading technique and the outer tubes will have normal welded closures.
Author: Publisher: ISBN: Category : Languages : en Pages : 7
Book Description
The objective of this production test is to authorize the irradiation of coextruded Zr-2 jacketed thick walled 1.6% enriched tubular elements in KER loops 1 and 2 to evaluate the swelling behavior of fuel elements at high uranium temperatures Coextruded Zr-2 jacketed 1.6% enriched tubular fuel elements 1.79 inch OD, 0.97 inch ID, and 12 inches long will be irradiated KER loops 1 and 2 to exposures no greater than 2500 MWD/T.
Author: J. H. Monaweck Publisher: ISBN: Category : Breeder reactors Languages : en Pages : 36
Book Description
This report summarizes the series of irradiations performed in the CP-5, MTR, and ETR on promising prototype EBR-II fuel elements. The exposure history and the effects of irradiation are described and illustrated photographically. These include dimensional and density changes, fission gas buildup, and fission product contamination of the sodium thermal bond, as a function of fuel burnup and operating temperature. The lesser physical changes evidenced by the stainless steel-clad uranium-fissium alloy support its superiority over the zirconium-uranium alloy, and ultimate selection for the initial core loading of the EBR-II.
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Author: J. L. Bates
Author: M. B. Watson
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Author: Richard C. Pugh
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Author: M. K. Millhollen
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Author: J. H. Monaweck