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Hart, R.R.; Rennie, J.; Aucoin, K.; West, M.
Amarillo National Resource Center for Plutonium, TX (United States). Funding organisation: USDOE, Washington, DC (United States); USDOE Office of Fissile Materials Disposition, Washington, DC (United States)1998
Amarillo National Resource Center for Plutonium, TX (United States). Funding organisation: USDOE, Washington, DC (United States); USDOE Office of Fissile Materials Disposition, Washington, DC (United States)1998
AbstractAbstract
[en] The effects of Ga from weapons-grade plutonium MOX fuel on zircaloy-IV cladding during power reactor operation have been simulated by implantations of 100 keV Ga-69 ions into a polished zircaloy-IV sample while the sample was maintained at a typical cladding temperature of 375 degrees C. Analyses were based on scanning electron microscopy, Rutherford backscattering of 280 keV He-3 ions, and secondary ion mass spectroscopy. Subgrains at the zircaloy-IV surface formed at a Ga fluence equivalent to total release of approximately 12 ppm by weight of Ga from the fuel. The subgrains may be an intermetallic compound of Zr2Ga. Enhanced diffusion of Ga was observed, but Ga concentrations decreased 3 orders of magnitude over a depth of 3000 angstrom
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May 1998; 24 p; CONTRACT FC04-95AL85832; ALSO AVAILABLE FROM OSTI AS DE98005698; NTIS; US GOVT. PRINTING OFFICE DEP
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Report
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ACTINIDES, ALLOYS, ALLOY-ZR98SN-4, CHROMIUM ADDITIONS, CORROSION RESISTANT ALLOYS, ELEMENTS, ENERGY SOURCES, FUELS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, IRON ADDITIONS, MATERIALS, METALS, NUCLEAR FUELS, REACTOR MATERIALS, REACTORS, SOLID FUELS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSURANIUM ELEMENTS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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