Compatibility of Uranium Carbide Fuels with Cladding Materials PDF Download
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Author: P. E. Elkins
Publisher:
ISBN:
Category : Carbides
Languages : en
Pages : 64
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Author: P. E. Elkins
Publisher:
ISBN:
Category : Carbides
Languages : en
Pages : 64
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Author: R. D. Hahn
Publisher:
ISBN:
Category : Carbides
Languages : en
Pages : 38
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Author:
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Category :
Languages : en
Pages :
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The contact compatibility (in the absence of sodium) between (U, Pu)C with equivalent carbon contents of 4.83, 5.25, and 6.75 wt % and iron-, nickel- and vanadium-base alloys was studied at 700-1100{deg}C for 168-4000 hr. Austenitic iron-base alloys, containing 25 wt % or less nickel and tested at 800{deg}C for up to 4000 hr, showed little or no evidence of carbon transfer from stoichiometric or hyperstoichiometric (U{sub 0.8}Pu{sub 0.2})C that contained up to 20 vol % (U, Pu)2C3. Three austenitic alloys containing more than 30 wt % nickel reacted with stoichiometric and hyperstoichiometric (U{sub 0.8}Pu{sub 0.2})C to form intermetallic compounds at the fuel-cladding interface and precipitates in the cladding at 700 and 800{deg}C. Vanadium-base alloys containing 15-20 wt % titanium were carburized by (U{sub 0.8}Pu{sub 0.2})C and reduced (U, Pu)P2C3 to (U, Pu)C at 800{deg}C. However, alloys containing 5 wt % or less titanium or other relatively strong carbide formers were only slightly affected by hyperstoichiometric (U, Pu)C at 800{deg}C for up to 4000 hr.
Author: T. W. Latimer
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 42
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Author: J. J. Finley
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Category : Niobium
Languages : en
Pages : 106
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Category : Nuclear energy
Languages : en
Pages : 978
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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 918
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Author:
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ISBN:
Category : Aeronautics
Languages : en
Pages : 1798
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Author: Odo Götzmann
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Category :
Languages : de
Pages : 7
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Author:
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ISBN:
Category : Energy development
Languages : en
Pages : 720
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