About this Abstract |
Meeting |
MS&T22: Materials Science & Technology
|
Symposium
|
Tackling Structural Materials Challenges for Advanced Nuclear Reactors
|
Presentation Title |
Deformation Behaviour of Ion-irradiated FeCr – A Nanoindentation Study |
Author(s) |
Kay Song, Hongbing Yu, Phani Karamched, Kenichiro Mizohata, David Armstrong, Felix Hofmann |
On-Site Speaker (Planned) |
Kay Song |
Abstract Scope |
Understanding the mechanisms of plasticity in structural steels is essential for the operation of next-generation fusion reactors. The study of ion-irradiated FeCr alloys is key to gaining a mechanistic understanding of irradiation damage in steels. This work on the deformation behaviour of FeCr, focusses on distinguishing between the nucleation of dislocations to initiate plasticity, from their propagation through the material. The effect of Cr content and irradiation dose on these dislocation mechanisms were examined through nanoindentation with a range of tip radii. Our results suggest that both Cr and irradiation-induced defects reduce the barrier for dislocation nucleation. However, pre-existing defects appear to be the dominant source. Yield strength, an indicator of dislocation mobility, increased with irradiation damage and Cr content, while work hardening capacity decreased. The synergistic effects of Cr and irradiation damage in FeCr appear to be more important for the propagation of dislocations than for their nucleation. |