About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
Quantification of radiation-induced nanoprecipitate dissolution mechanisms in Fe-based binary alloys |
| Author(s) |
Yajie Zhao, Pengcheng Zhu, Steven Zinkle |
| On-Site Speaker (Planned) |
Yajie Zhao |
| Abstract Scope |
Nano-sized precipitates are commonly introduced to improve the performance of ferritic–martensitic steels for nuclear applications. However, their stability may degrade under irradiation exposure, which is known to depend on the radiation-enhanced diffusion (RED) and radiation mixing, and the latter remains poorly quantified. This study aims to isolate and evaluate the radiation-induced dissolution by using low-temperature irradiations to suppress precipitate recovery from RED. Model FeCr and FeCu alloys were thermally aged at 475 °C (100 and 900h) and 500 °C (1.5 and 10h), respectively, to form nanoscale Cr-rich and Cu-rich precipitates. They were then irradiated with 8 MeV Fe ions at −123 °C or room temperature to 0.1, 0.2 and 0.6 displacement per atom (dpa). Atom probe tomography characterization revealed that precipitate size and number density remain largely constant, whereas solute concentration within precipitates and matrix decreased and increased with dose, respectively. This dissolution behavior was tentatively rationalized with displacement cascade events and irradiation dose. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Iron and Steel, Phase Transformations |