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Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing Public Deposited

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https://ir.library.oregonstate.edu/concern/articles/47429b96r

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  • The High Performance Research Reactor Fuel Development (HPPRFD) program is responsible for developing low enriched uranium (LEU) fuel substitutes for high performance reactors fueled with highly enriched uranium (HEU) that have not yet been converted to LEU. The uranium-molybdenum (U-Mo) fuel system was selected for this effort. In this study, fission gas pore segmentation was performed on U-7wt%Mo dispersion fuel samples at three separate fission densities using an automated image processing interface developed in MATLAB. Pore size distributions were attained that showed both expected and unexpected fission gas behavior. In general, it proved challenging to identify any dominant trends when comparing fission bubble data across samples from different fuel plates due to varying compositions and fabrication techniques. The results exhibited fair agreement with the fission density vs. porosity correlation developed by the Russian reactor conversion program.
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  • Collette, R., King, J., Buesch, C., Keiser, D. D. Jr, Williams, W., Miller, B. D., & Schulthess, J. (2016). Analysis of irradiated U-7wt% Mo dispersion fuel microstructures using automated image processing. Journal of Nuclear Materials, 475, 94-104. doi:10.1016/j.jnucmat.2016.03.028
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  • This work was supported by the U.S. Department of Energy, Office of Material Management and Minimization, National Nuclear Security Administration, under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517.
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