|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Ion Irradiation Effects on Microstructure Evolution and Mechanical Properties of Silicon Oxycarbide
||Kathy Lu, Sanjay Kumar Singh, Kaustubh Bawane
|On-Site Speaker (Planned)
Polymer derived ceramic is a promising nuclear material due to its irradiation resistant and high temperature stable nature. In this study, silicon oxycarbide (SiOC) was fabricated by pyrolysis of a polysiloxane precursor polymer at 1000°C and 1500°C in an Ar atmosphere. The 1000°C pyrolyzed SiOC is fully amorphous while the 1500°C sample involves crystalline β-SiC nanodomains, turbostratic carbon network, and amorphous SiOC. After 100 keV He ion irradiation, there is no detectable microstructural changes for the 1000°C pyrolyzed SiOC. However, the 1500°C pyrolyzed SiOC shows amorphization. Neither sample has He bubbles, elemental segregation or voids as a result of irradiation. Raman studies showed effect of irradiation on Si-O-C bonding. Irradiation temperature has no perceivable effect on microstructure and mechanical properties of SiOC. This work offers important guidance for development of radiation-tolerant polymer derived SiOC materials with applications in advanced nuclear reactors.
||Ceramics, Characterization, Nuclear Materials