About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
|
| Presentation Title |
Development of in-situ irradiation creep testing and application to a ferritic-martensitic steel |
| Author(s) |
Dave Lunt, Benjamin Poole, Thomas Hughes, Philipp Frankel, Ed Pickering, Samir de Moraes Shubeita, Allan Harte, Cory Hamelin, Chris Hardie |
| On-Site Speaker (Planned) |
Dave Lunt |
| Abstract Scope |
Understanding of material degradation mechanisms in a nuclear environment, such as STEP, is currently focussed on testing parameters (mechanical, thermal or irradiation) in isolation. This lack of a realistic assessment of component performance leads to materials for fusion being considered for longer than necessary. Here, we detail the commissioning and implementation of synergistic irradiation-thermomechanical testing capability at Dalton Cumbrian Facility, which has been developed as part of the materials validation strategy for STEP. This capability has been used to compare the thermal and irradiation creep response of a ferritic-martensitic steel under the anticipated fusion environment. Developing capability to improve the understanding of irradiation-enhanced creep is important for timely qualification of high temperature materials for STEP, given that long-term performance phenomena is not well understood. Furthermore, deformation has been quantified at multiple length-scales using in-situ optical digital image correlation and deformation mechanisms determined from ex-situ high-resolution strain mapping at the grain-scale. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Iron and Steel, Nuclear Materials |