About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Evolution of Dislocation Structure and Defects in Additively Manufactured 316 Stainless Steels Under Ion Irradiation – A Cluster Dynamics Study |
| Author(s) |
Sanjoy Kumar Mazumder, Wei-Ying Chen, Matthew Swisher, Stephen Taller, Andrea Jokisaari |
| On-Site Speaker (Planned) |
Sanjoy Kumar Mazumder |
| Abstract Scope |
The unique radiation damage behaviors of ion-irradiated additively manufactured (AM) 316 stainless steels are investigated via a novel mean-field cluster dynamics (CD) framework, with a focus on dislocation cells and voids. AM316 stainless steel is a potential structural material for advanced reactors. TEM analysis of AM316, irradiated with 4 MeV Ni ions to 10 dpa at 300 and 600oC, showed the cellular microstructure evolves into network dislocations, with both nucleation and growth of a spatially heterogenous void population at the former cell walls. The CD framework couples the evolution of point defects, small clusters, dislocation loops and voids, with concurrent annihilation of network dislocations within the cells and in cell walls by a dislocation climb-glide mechanism. Interaction of irradiation-induced dislocation loops with cell walls and network dislocations are also considered. Preliminary results show a steady decline in the dislocation density at cell walls, up to 1 dpa. Also, predictions from the CD model accurately reproduces the evolution of dislocation loop and void population, with irradiation dose. The experimentally observed swelling behavior of AM316 steels with irradiation temperature and doserate, was also closely predicted by the CD model. |
| Proceedings Inclusion? |
Undecided |