About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
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Symposium
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Characterization of Nuclear Materials and Fuels with Advanced X-ray and Neutron Techniques
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Presentation Title |
Synchrotron Microdiffraction Study of Cracks and Indentation on UO2 Material |
Author(s) |
Kun Mo, Yinbin Miao, Ruqing Xu, Tiankai Yao, Jie Lian, Laura Jamison, Abdellatif Yacout |
On-Site Speaker (Planned) |
Yinbin Miao |
Abstract Scope |
During operation of light water reactors, uranium dioxide (UO2) experiences both high temperature and large temperature gradients across the fuel pin. As UO2 lacks macroscopic plasticity, fractures and cracks are commonly found in fuel pellets. In this study, we applied an advanced synchrotron micro X-ray diffraction (μXRD) technique to study lattice strain development in cracking and indentation regions of micro-indented UO2 material, which was prepared by spark plasma sintering (SPS). Two of the indentations in the UO2 sample surface were selected to be studied by synchrotron µXRD. A method to corelate microstructures (cracks and other defects) observed in SEM and micro-diffraction measurements was presented. On the indented UO2 sample, the highest and lowest strained areas were found near the indentation tip and within the “open” crack, respectively. Induced by the residual stress, the lattice strain near the indentation was found to progressively decrease from the indentation boundary outwards. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Other |