| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
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| Symposium
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Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
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| Presentation Title |
Microstructural and Micro-chemical Characterization of Safety Tested TRISO UCO Fuel Kernels Irradiated in the Advanced Test Reactor
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| Author(s) |
Zhenyu Fu, Lingfeng He, Xiang Liu, Isabella van Rooyen, Yong Yang |
| On-Site Speaker (Planned) |
Zhenyu Fu |
| Abstract Scope |
In this study, the AGR-2-222-RS36 and AGR-2-222-RS19 TRISO fuel particles were irradiated to a burnup of 12.55% FIMA in ATR, followed by safety testing at 1600ºC for 300 hours. Transmission electron microscopy (TEM) lamellas were prepared at the fuel kernel center, half center, recoil zone, and the fuel kernel-buffer layer interface. The Talos F200X scanning/TEM (STEM) was used to characterize the microstructural and micro-chemical evolutions in those two irradiated fuel kernels. Preliminary data analysis gives the following findings: (1) Rod-shaped precipitates rich in fission product Pd are scattered from the fuel kernel center to the edge; (2) Sub-micro and nano-sized precipitates rich in fission product Pd, Rh, and Ag are located in the buffer layer; (3) Amorphous carbon is found to diffuse into the fuel kernel up to a distance of 50 m from the kernel outer surface; and (4) Fission gas bubbles were mainly observed in the Mo-rich phase. |
| Proceedings Inclusion? |
Undecided |