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Aluminum cladding oxidation of prefilmed in-pile fueled experiments Public Deposited

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https://ir.library.oregonstate.edu/concern/articles/xg94hr41r

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  • A series of fueled irradiation experiments were recently completed within the Advanced Test Reactor Full size plate In center flux trap Position (AFIP) and Gas Test Loop (GTL) campaigns. The conduct of the AFIP experiments supports ongoing efforts within the global threat reduction initiative (GTRI) to qualify a new ultra-high loading density low enriched uranium-molybdenum fuel. This study details the characterization of oxide growth on the fueled AFIP experiments and cross-correlates the empirically measured oxide thickness values to existing oxide growth correlations and convective heat transfer correlations that have traditionally been utilized for such an application. This study adds new and valuable empirical data to the scientific community with respect to oxide growth measurements of highly irradiated experiments, of which there is presently very limited data. Additionally, the predicted oxide thickness values are reconstructed to produce an oxide thickness distribution across the length of each fueled experiment (a new application and presentation of information that has not previously been obtainable in open literature); the predicted distributions are compared against experimental data and in general agree well with the exception of select outliers.
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  • Marcum, W. R., Wachs, D. M., Robinson, A. B., & Lillo, M. A. (2016). Aluminum Cladding Oxidation of Prefilmed In-Pile Fueled Experiments. Journal of Nuclear Materials, 471, 136-148. doi:10.1016/j.jnucmat.2016.01.011
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  • 471
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  • This work was partially supported by the U.S. Department of Energy, Office of Nuclear Materials Threat Reduction (NA-212), National Nuclear Security Administration, under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517.
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