About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
|
Symposium
|
Elucidating Microstructural Evolution Under Extreme Environments
|
Presentation Title |
Cavity and Dislocation Loop Evolution in Neutron Irradiated 800H Alloy |
Author(s) |
Antoine Waegaert, Xingyu Liu, Xing Wang, Arthur T. Motta |
On-Site Speaker (Planned) |
Antoine Waegaert |
Abstract Scope |
To accelerate the qualification process of structural materials for advanced nuclear reactors and life-extended operating reactors, the austenitic 800H alloy is selected as a convenient benchmark for emulating neutron damage in face-centered cubic materials using dual ion irradiation at high doses. Samples were neutron-irradiated in the BOR-60 research reactor, to a total damage level up to 72 dpa. Transmission electron microscope was used to measure the density and size distribution of cavities and faulted loops after-irradiation. The swelling in the neutron irradiated samples increased monotonically with dose, both the cavity size and cavity density increasing with dose. The radiation-induced faulted dislocation loops, increased at the initial stage of irradiation and saturated at high doses due to the unfaulting process. The cavity size distributions were characterized and shown also to increase steadily with dose. |
Proceedings Inclusion? |
Planned: |
Keywords |
Characterization, Nuclear Materials, Iron and Steel |