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

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

To the best of our knowledge, one or more authors of this paper were federal employees when contributing to this work. This is the publisher’s final pdf. The published article is copyrighted by Elsevier and can be found at:  http://www.journals.elsevier.com/journal-of-nuclear-materials/

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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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  • description.provenance : Submitted by Patricia Black (patricia.black@oregonstate.edu) on 2016-07-01T18:25:38Z No. of bitstreams: 1 ColletteAnalysisofIrradiatedU7wt.pdf: 2769414 bytes, checksum: b49ea42c1f5f51c0cb825d22e86b93af (MD5)
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