Title

Constituent Redistribution In U-Pu-Zr Fuel During Irradiation

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. © 2004 Elsevier B.V. All rights reserved.

Publication Date

4-1-2004

Publication Title

Journal of Nuclear Materials

Volume

327

Issue

1

Number of Pages

27-36

Document Type

Article

Personal Identifier

scopus

DOI Link

https://doi.org/10.1016/j.jnucmat.2004.01.012

Socpus ID

1642356341 (Scopus)

Source API URL

https://api.elsevier.com/content/abstract/scopus_id/1642356341

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