About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
|
| Presentation Title |
Irradiation temperature and mechanical properties in neutron irradiated ferritic steel |
| Author(s) |
Benjamin P. Eftink, Tarik Saleh, Dominic Piedmont, James Stubbins, Mychailo Toloczko, Stuart Maloy |
| On-Site Speaker (Planned) |
Benjamin P. Eftink |
| Abstract Scope |
One of the fundamental interrelated extremes for structural materials in fission or fusion reactor environments is irradiation and temperature. Resultant mechanical properties depend strongly on irradiation temperature. In the results that will be shown on HT-9 steel, irradiation temperature has a more profound impact than irradiation dose on the mechanical properties. This talk will go over the mechanical properties of a reactor relevant ferritic steel irradiated at different temperatures in two different fast neutron spectrum nuclear reactors. These include tensile testing of HT-9 ferritic/martensitic reactor fuel duct that was in service in the FFTF sodium cooled fast reactor, providing irradiation temperatures in the range of 380 and 500 C. Additionally, shear punch testing of HT-9 irradiated in the BOR-60 sodium cooled fast reactor at a similar temperature range for comparison. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Iron and Steel, Nuclear Materials |