About this Abstract |
| Meeting |
2027 TMS Annual Meeting & Exhibition
|
| Symposium
|
Enabling Nuclear Materials Innovation via the Nuclear Science User Facility Capabilities
|
| Presentation Title |
Enabling the Understanding of Irradiation Effects and Performance in Fe-Cr Ferritic Alloys |
| Author(s) |
James F. Stubbins |
| On-Site Speaker (Planned) |
James F. Stubbins |
| Abstract Scope |
The evolution of understanding of irradiation effects in a number of Fe-Cr base model and commercial alloys based on irradiation and post-irradiation examination through the NSUF will be covered. These developments started with the Advanced Test Reactor irradiation of a number of Fe-Cr alloys from temperatures at 300°C up to 550°C in dose increments from 0.01 dpa to 10 dpa. Following irradiation, the model and commercial alloys have been examined using microstructural facilities at a number of NSUF sites and, in many cases, also provided significant information about post-irradiation mechanical properties the microstructural basis of the irradiation-induced changes. More recently, improvements in synchrotron capabilities have permitted the development of 3D bulk materials characterization which has added to the supporting information from SEM, TEM, and atom probe local microstructural and microchemical features. The impact of this work on materials application and development for current and advanced nuclear systems will be discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Nuclear Materials |