Characterization of Au Irradiated Glassy Polymeric Carbon at 2,000°C for Nuclear Applications
The TRISO fuel has been used in some of the Generation IV nuclear reactor designs . It consists of a fuel kernel of UOx coated with several layers of materials with different functions. Pyrolytic carbon (PyC) is one of the materials in the layers. In this study we investigate the possibility of using Glassy Polymeric Carbon (GPC) as an alternative to PyC. In this work, we are comparing the changes in physical and microstructure properties of GPC after exposure to irradiation fluence of 5 MeV Au equivalent to a 1 displacement per atom (dpa) for GPC prepared at 2,000°C. The GPC material is manufactured and tested at the Center for Irradiation Materials (CIM) at Alabama A&M University using Transmission electron microscopy (TEM) and stopping range of ions in matter (SRIM) software.
KeywordsTransmission electron spectroscopy Glassy polymeric carbon
This research was supported and funded by the AAMRI Center for Irradiation of Material, NSF Alabama GRSP EPSCOR, and DoE NERI-C project number DE-FG07-07ID14894. Acknowledgment also goes for Dr. Edwards, the Dean of the school of Arts and Sciences at Alabama A&M University for the travel support.
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