| About this Abstract |
| Meeting |
MS&T24: Materials Science & Technology
|
| Symposium
|
Tackling Metallic Structural Materials Challenges for Advanced Nuclear Reactors
|
| Presentation Title |
Characterization of In Situ and Ex Situ Ion Irradiated AM316L and AM316H Stainless Steels |
| Author(s) |
Wei-Ying Chen, Stephen Taller, Andrea Jokissari, Yiren Chen, Rongjie Song |
| On-Site Speaker (Planned) |
Wei-Ying Chen |
| Abstract Scope |
Additively manufactured (AM) 316 stainless steel differs from its wrought counterpart in its unique dislocation cell structure and the MnSiO3 particles decorating the cell wall. This work investigated the evolution of defects in both AM316L and AM316H under in-situ 1 MeV Kr ion irradiation and ex-situ 4 MeV Ni ion irradiation at 300°C and 600°C with a dose rate of 10-3 dpa/s up to 10 dpa. Results reveal that the dislocation cell structure profoundly affect the formation of dislocation loops and voids, particularly at 600°C, where loops tend to form within cell interior while voids form at cell boundaries. AM316H had reduced swelling compared to AM316L. At 300°C, where voids are absent, defect distribution appears to be more uniform. Additionally, the precipitation, segregation, and the comparison with available neutron data on wrought 316 will be discussed. |