NSUF 17-728: Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel
Austenitic stainless steel NF709 has been down-selected for development as a candidate structural materials for sodium-cooled fast reactors. However, the understanding on its radiation resistance is limited to a few model or simplified alloys. Our recent firsthand microstructural characterization indicated significant evolution of precipitates in NF709 after irradiation to 3 displacements per atom (dpa) at 500°C. To better understand radiation resistance of NF709, this project is to study radiation-hardening and microstructural evolution of NF709 irradiated to 6 dpa at 400, 500, and 700°C. The outcome of this study will provide key insights to understand radiation resistance of Alloy 709 that is optimized from NF709 under the Advanced Reactor Technologies (ART) program.
額外的資訊
| 欄位 | 值 |
|---|---|
| Abstract | Austenitic stainless steel NF709 has been down-selected for development as a candidate structural materials for sodium-cooled fast reactors. However, the understanding on its radiation resistance is limited to a few model or simplified alloys. Our recent firsthand microstructural characterization indicated significant evolution of precipitates in NF709 after irradiation to 3 displacements per atom (dpa) at 500°C. To better understand radiation resistance of NF709, this project is to study radiation-hardening and microstructural evolution of NF709 irradiated to 6 dpa at 400, 500, and 700°C. The outcome of this study will provide key insights to understand radiation resistance of Alloy 709 that is optimized from NF709 under the Advanced Reactor Technologies (ART) program. |
| Award Announced Date | 2017-04-24T10:10:01.383 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kory Linton |
| Irradiation Facility | None |
| PI | Lizhen Tan |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 728 |