About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Accelerated Discovery and Qualification of Nuclear Materials for Energy Applications
|
Presentation Title |
Comparison of Void Swelling in Conventional and Novel HT9 Alloys after High Damage Level Ion Irradiation |
Author(s) |
Hyosim Kim, Jonathan Gregory Gigax, Osman El Atwani, Stuart Andrew Maloy, Yongqiang Wang, Matthew Ryan Chancey, Jon Kevin Scott Baldwin |
On-Site Speaker (Planned) |
Hyosim Kim |
Abstract Scope |
HT9 is a conventional cladding and structural material that is used in nuclear reactors, with an extensive history in service due to its superior radiation tolerance up to ~200 dpa. While conventional HT9 alloys, such as the INL and ACO-3 heats, have been studied after both neutron and ion irradiation, novel alloys such as nitrogen modified heats, have not been investigated in such detail. We utilized Fe self-ion irradiation at 450 °C to irradiate conventional (INL, AC03) and novel (Low N, High N) HT9 alloys up to 600 peak dpa. The INL and ACO-3 heats showed a similar swelling response. The low N heat exhibited the largest amount of swelling, about twice more than the conventional heats. However, the high N heat showed the least amount of swelling, with one third the swelling of the conventional heats and an order of magnitude less than the low N heat. |
Proceedings Inclusion? |
Planned: |