Abstract
Characterizing oxide nuclear fuels is difficult due to complex fission products, which result from time-evolving system chemistry and extreme operating environments. Here, we report a machine learning-enhanced approach that accelerates the characterization of spent nuclear fuels and improves the accuracy of identifying nanophase fission products and bubbles. We apply this approach to commercial, high-burnup, irradiated light-water reactor fuels, demonstrating relationships between fission product precipitates and gases. We also gain understanding of the fission versus decay pathways of precipitates across the radius of a fuel pellet. An algorithm is provided for quantifying the chemical segregation of the fission products with respect to the high-burnup structure, which enhances our ability to process large amounts of microscopy data, including approaching the atomistic-scale. This may provide a faster route for achieving physics-based fuel performance modeling.
Original language | English |
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Article number | 21 |
Journal | Communications Materials |
Volume | 3 |
Issue number | 1 |
DOIs | |
State | Published - Dec 2022 |
Funding
This research was sponsored by the Transformational Challenge Reactor program and supported by the US Department of Energy (DOE), Office of Nuclear Energy and Office of Science, Fusion Energy Sciences. This research was conducted, in part, using instrumentation (FEI Talos F200X S/TEM) supported by the US DOE, Office of Nuclear Energy, Fuel Cycle Research and Development and the Nuclear Science User Facilities. A portion of this research was conducted at ORNL’s Center for Nanophase Materials Sciences, a DOE Office of Science User Facility. This research was supported in part by the Oak Ridge National Laboratory (ORNL) postdoc development funds and an appointment to the ORNL Higher Education Research Experience Program, sponsored by the US DOE and administered by the Oak Ridge Institute for Science and Education. The authors are indebted to a multitude of facilities and support personnel at ORNL that enabled fuel specimen handling, preparation, and extraction from the hot cell. Specifically, the assistance of staff of the Low Activation Materials Design and Analysis Laboratory and Irradiated Fuels Examination Laboratory is gratefully acknowledged. K.D. Linton and J.W. Werden offered their critical support and advice. The authors also would like to thank L.R. Scime and R.L. Seibert for discussing the results, providing fruitful comments, and reviewing the paper.
Funders | Funder number |
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Fuel Cycle Research and Development | |
U.S. Department of Energy | |
Office of Science | |
Office of Nuclear Energy | |
Fusion Energy Sciences | |
Oak Ridge National Laboratory | |
Oak Ridge Institute for Science and Education |