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Effects of Thermal Treatment on the Co-rolled U-Mo Fuel Foils

Published online by Cambridge University Press:  27 April 2015

Jan-Fong Jue
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Dennis D. Keiser
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Tammy L. Trowbridge
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Cynthia R. Breckenridge
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Brady L. Mackowiak
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Glenn A. Moore
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Barry H. Rabin
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
Mitchell K. Meyer
Affiliation:
Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415, U.S.A.
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Abstract

A monolithic fuel design based on U–Mo alloy has been selected as the fuel type for conversion of United States’ high-performance research reactors (USHPRRs) from highly enriched uranium (HEU) to low-enriched uranium (LEU). In this fuel design, a thin layer of zirconium is used to eliminate the direct interaction between the U–Mo fuel meat and the aluminum-alloy cladding during irradiation. The co-rolling process used to bond the Zr barrier layer to the U–Mo foil during fabrication alters the microstructure of both the U–10Mo fuel meat and the U–Mo/Zr interface. This work studied the effects of post-rolling annealing treatment on the microstructure of the co-rolled U–Mo fuel meat and the U–Mo/Zr interaction layer. The U–Mo/Zr interaction-layer thickness increased with the annealing temperature with an Arrhenius constant for growth of 184kJ/mole, consistent with a previous diffusion-couple study. The phases in the U–Mo/Zr interaction layer produced by co-rolling, however, differ from those reported in the previous diffusion-couple study.

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Articles
Copyright
Copyright © Materials Research Society 2015 

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References

Meyer, M. K, Hofman, G. L., Hayes, S. L., Clark, C. R., Wiencek, T. C., Snelgrove, J. L., Strain, R. V., and Kim, K.-H., Journal of Nuclear Materials 304 221236 (2002).CrossRef
Keiser, D. D. Jr., Robinson, A. B., Jue, J.-F., Medevedev, P., Wachs, D. M. and Finlay, M. R., Journal of Nuclear Materials, 393 311320 (2009).CrossRef
Leenaers, A., Van den Berghe, S., Van Eyken, J., Koonen, E., Charollais, F., Lemoine, P., Galzavara, Y., Guyon, H., Jarousse, C., Geslin, D., Wachs, D., Keiser, D., Robinson, A., Hofman, G., Kim, Y. S., Journal of Nuclear Materials 443 439448 (2013).CrossRef
Perez, E., Yao, B., Keiser, D. D. Jr., and Sohn, Y. H., Journal of Nuclear Materials 402 814 (2010).CrossRef
Jue, Jan-Fong, Keiser, Dennis D. Jr., Breckenridge, Cynthia R., Moore, Glenn A., and Meyer, Mitchell K., Journal of Nuclear Materials 448 250258 (2014).CrossRef
Huang, K., Park, Y., Keiser, D. D. Jr., and Sohn, Y. H., Journal of Phase Equilibria and Diffusion 33 443449 (2012).CrossRef

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