About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
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Symposium
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Advanced Characterization and Modeling of Nuclear Fuels: Microstructure, Thermo-physical Properties
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Presentation Title |
N-5: Characterization of Additively Manufactured UO2 Fuel Pellets with Pulsed Neutron Techniques and 450 keV X-ray CT |
Author(s) |
Sven C. Vogel, Donald W. Brown, Bjorn Clausen, Alexander M. Long, Erik B. Watkins, D. Cort Gautier, Cheryl Kendall, Cheng Sun, Chuting Tan |
On-Site Speaker (Planned) |
Sven C. Vogel |
Abstract Scope |
In recent years, significant development of advanced manufacturing technologies allows novel designs to overcome limitations imposed by conventional nuclear fuel fabrication methods and fabricate fuel geometries that accommodate swelling much better, hence enabling higher burnup and therefore improve the economy of nuclear power generation. To develop and ultimately license additively manufactured nuclear fuels, characterization of the 3D-printed fuel pellets is required. While optical, X-ray and electron-based techniques can characterize essentially the surface of such materials, few bulk characterization methods exist to probe entire fuel pellets (~1 ccm). Here, we report the non-destructive characterization of two annular UO2 fuel element fabricated via digital light processing using neutron diffraction, neutron CT as well as 450 keV high resolution X-ray CT. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Additive Manufacturing, Characterization |