Modeling of constituent redistribution in U–Pu–Zr metallic fuel

A computer model was developed to analyze constituent redistribution in U–Pu–Zr metallic nuclear fuels. Diffusion and thermochemical properties were parametrically determined to fit the postirradiation data from a fuel test performed in the Experimental Breeder Reactor II (EBR-II). The computer mode...

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Veröffentlicht in:	Journal of nuclear materials 2006-12, Vol.359 (1), p.17-28
Hauptverfasser:	Kim, Yeon Soo, Hayes, S.L., Hofman, G.L., Yacout, A.M.
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences BREEDER REACTORS COMPUTERS DIFFUSION Energy Energy. Thermal use of fuels Exact sciences and technology FAST REACTORS Fission nuclear power plants Installations for energy generation and conversion: thermal and electrical energy NUCLEAR FUEL CYCLE AND FUEL MATERIALS NUCLEAR FUELS SIMULATION SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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