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- W113835124 abstract "To optimize and better understand fuel element behavior in integral fast reactors, the compatibility of U-Pu-Zr fuel with various cladding steel alloys is being investigated. Interaction between fuel and cladding during irradiation of a fuel element can result in the formation of phases that degrade the performance of the cladding, and as a result, diffusion couple techniques have been employed to study the relative interdiffusion behavior of fuel and cladding components. Early investigations assessed the interdiffusion behavior in couples assembled with a binary U-Zr alloy and selected alloys in the Fe-Ni-Cr system and selected cladding steels and in a U-21 Pu-23 Zr fuel alloy coupled with HT9 cladding steel (the nominal composition in weight percent for HT9 is 12 Cr-0.6 Ni-1 Mo-0.3 V-0.5 W-0.5 Mn-0.2 Si-0.2 C-bal Fe). The purpose of this investigation was to compare the interdiffusion behavior in a diffusion couple composed of U-21 Pu-23 Zr fuel and austenitic D9 cladding steel (the nominal composition in weight percent for D9 is 13.4 Cr-15.6 Ni-1.7 Mo-0.3 Ti-2.1 Mn-0.9 Si-0.03 C-bal Fe) with the behavior reported in earlier fuel versus cladding steel investigations and to study the relative interdiffusion behavior of the various fuel and cladding steel components in themore » presence of plutonium.« less" @default.
- W113835124 created "2016-06-24" @default.
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- W113835124 date "1994-12-31" @default.
- W113835124 modified "2023-09-27" @default.
- W113835124 title "Interdiffusion behavior in couples between U-Pu-Zr fuel and cladding steels" @default.
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