About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
2026 Technical Division Student Poster Contest
|
| Presentation Title |
SPG-75: Defect Structure Evolution in Irradiated 316 Stainless Steel and Implications for Tritium Transport |
| Author(s) |
Charles Perkins, Chris McRobie, Danny Edwards, Jacob Haag, Michael Lastovich, Fu-Yun Tsai, Syed Rizvi, Caleb Schenck, Ming Liu, Joshua Silverstein, David Senor, Andrew Casella, Elizabeth Kautz, Bharat Gwalani |
| On-Site Speaker (Planned) |
Charles Perkins |
| Abstract Scope |
An understanding of defect structures and their evolution in irradiated 316 stainless steel (316SS) is important for predicting tritium transport and retention in the cladding of a Tritium Producing Burnable Absorber Rod (TPBAR). This work examines the formation, distribution and evolution of defects generated in 316SS during irradiation and their behavior during post-irradiation annealing (PIA). Permeation and trapping of tritium is influenced by point defects, dislocations, grain boundaries, precipitates, and irradiation-induced chemical segregation. Although irradiation effects in austenitic stainless steels have been widely studied, the relative populations of vacancy and interstitial type defects, their spatial distribution, and their evolution during thermal recovery are still unknown. A characterization approach involving irradiated TPBAR cladding and model austenitic systems is used to characterize defects and their evolution. Characterization techniques include positron annihilation lifetime spectroscopy (PALS), transmission electron microscopy (TEM), and high-temperature mechanical testing to examine defect populations across length scales. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
Iron and Steel, Nuclear Materials, Characterization |