Title

Constituent redistribution in U-Pu-Zr fuel during irradiation

Authors

Authors

Y. S. Kim; G. L. Hofman; S. L. Hayes;Y. H. Sohn

Comments

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Abbreviated Journal Title

J. Nucl. Mater.

Keywords

FAST-REACTOR FUEL; TEMPERATURE-GRADIENT; THERMAL-GRADIENT; ALLOYS; BEHAVIOR; Materials Science, Multidisciplinary; Nuclear Science & Technology; Mining & Mineral Processing

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 gamma, gamma + zeta and delta + zeta 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. (C) 2004 Elsevier B.V. All rights reserved.

Journal Title

Journal of Nuclear Materials

Volume

327

Issue/Number

1

Publication Date

1-1-2004

Document Type

Article

Language

English

First Page

27

Last Page

36

WOS Identifier

WOS:000220576600004

ISSN

0022-3115

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