|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Characterization of Minerals, Metals and Materials 2021
||Rapid Irradiation and Characterization of HT9
||Gabriella Bruno, Kevin Field, Li He, T.M. Kelsy Green, Todd Allen
|On-Site Speaker (Planned)
Advanced nuclear reactor designs call for unprecedently high damage levels when compared to traditional reactors. Simulating the expected damage can be done with ion irradiations, which achieves damage levels greater than reactors while also capturing the physics of the radiation damage processes. Here, we demonstrate this methodology using HT9, a 12 wt.% chromium, ferritic-martensitic steel. Dual-ion (Fe3+ & He2+) irradiations were controlled to 445+/-15°C, 460+/-15°C, 570+/-15°C at a damage level of 26 dpa and 4 appm He/dpa with an estimated He production of 0.22 appm He/dpa. STEM imaging and composition mapping were used. The cavity number density peaks around 460°C. Dislocation loops decreased in number density and increased in size with increasing temperature. Segregation to the grain boundaries are evident below 460°C and decreases at temperatures above 460°C. Overall, we will show how the present trends based on ion irradiation temperature replicate the expected behavior during fast reactor service.
||Nuclear Materials, Characterization, High-Temperature Materials