| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Bridging Microscale to Macroscale Mechanical Property Measurements and Predication of FeCrAl Alloys Under Extreme Reactor Applications |
| Author(s) |
Jian Wang, Xinghang Zhang, Lin Shao |
| On-Site Speaker (Planned) |
Jian Wang |
| Abstract Scope |
Microscale mechanical testing has greatly benefited nuclear materials studies in at least two aspects: one is its feasibility to integrate with SEM and TEM microscopes for in situ atomic scale or microscale structural characterization to reveal fundamental details, and the other is its significance in development of accelerator-based ion irradiation technique as a surrogate method to simulate neutron damage. But, there is a great challenge to bridge microscale tests to macroscale tests because a bulk specimen of irradiated nuclear materials for high dose applications cannot be obtained in laboratory. We synthesized single phase FeCrAl (CM35) alloys and measured stress-strain response of bulk samples and micropillars with different thermal treatments at different temperatures and irradiation conditions. We developed an integrated theoretical, modeling, and experimental platform that enables predicting the ductility of nuclear structural materials based on microscale mechanical tests. |
| Proceedings Inclusion? |
Planned: |