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Constituent redistribution in U-Pu-Zr fuel during irradiation |
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| Authors: | Yeon Soo Kim G.L Hofman Y.H Sohn |
| Affiliation: | a Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439, USA b Argonne National Laboratory, Idaho Falls, ID 83403-2528, USA c University of Central Florida, 4000 Central Florida Blvd., Orlando, FL 32816-2455, USA |
| Abstract: | The thermo-migration fluxes of U, Pu and Zr in U-Pu-Zr metallic alloy fuel during irradiation in the Experimental Breeder Reactor II (EBR-II) were calculated using the constituent redistribution profiles measured in postirradiation examinations. Based on these fluxes, the diffusion coefficients, and the sums of heat of transport and enthalpy of solution for the γ, γ+ζ and δ+ζ phases in U-Pu-Zr were obtained. Using these data, the predicted concentration redistribution profiles are consistent with the measurements. The effect of minor actinide (Am and Np) addition was also examined. Am migration generally followed that of Zr with local precipitation, while Np behaved similarly to Pu. |
| Keywords: | C0200 D0300 F0700 N0100 U0100 |
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