Constituent redistribution in U-Pu-Zr fuel during irradiation

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

doi:10.1016/j.jnucmat.2004.01.012

Constituent redistribution in U-Pu-Zr fuel during irradiation

Yeon Soo Kim
, G. L. Hofman
, S. L. Hayes
, Y. H. Sohn

Research output: Contribution to journal › Article › peer-review

95 Scopus citations

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.

Original language	English
Pages (from-to)	27-36
Number of pages	10
Journal	Journal of Nuclear Materials
Volume	327
Issue number	1
DOIs	https://doi.org/10.1016/j.jnucmat.2004.01.012
State	Published - Apr 1 2004
Externally published	Yes

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10.1016/j.jnucmat.2004.01.012

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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.",

author = "Kim, \{Yeon Soo\} and Hofman, \{G. L.\} and Hayes, \{S. L.\} and Sohn, \{Y. H.\}",

note = "Funding Information: This work has been created by the University of Chicago as Operator of Argonne National Laboratory under contract no. W-31-109-ENG-38 with the US Department of Energy. ",

year = "2004",

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doi = "10.1016/j.jnucmat.2004.01.012",

language = "English",

volume = "327",

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T1 - Constituent redistribution in U-Pu-Zr fuel during irradiation

AU - Kim, Yeon Soo

AU - Hofman, G. L.

AU - Hayes, S. L.

AU - Sohn, Y. H.

N1 - Funding Information: This work has been created by the University of Chicago as Operator of Argonne National Laboratory under contract no. W-31-109-ENG-38 with the US Department of Energy.

PY - 2004/4/1

Y1 - 2004/4/1

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/1642356341

U2 - 10.1016/j.jnucmat.2004.01.012

DO - 10.1016/j.jnucmat.2004.01.012

M3 - Article

AN - SCOPUS:1642356341

SN - 0022-3115

VL - 327

SP - 27

EP - 36

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1

ER -

Constituent redistribution in U-Pu-Zr fuel during irradiation

Abstract

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