| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications II
|
| Presentation Title |
Characterization of the Effects of Intermediate Temperature Neutron Irradiation on Model Fe-Cr Alloys |
| Author(s) |
Dhriti Bhattacharyya, Alan Xu, Takuya Yamamoto, G. Robert Odette |
| On-Site Speaker (Planned) |
Dhriti Bhattacharyya |
| Abstract Scope |
Ferritic and ferritic-martensitic steels with high Cr and stable oxide precipitates (e.g. ODS steels) show improved resistance to radiation damage and creep. However, irradiation enhanced diffusion is known to cause precipitation of Cr in the form of α' clusters. Moreover, irradiation by neutrons causes the formation of various defects, e.g., loops and dislocations.
Here, we present TEM studies on a series of Fe-Cr alloys (Fe-3%Cr - Fe-18%Cr), irradiated in the Advanced Test Reactor at INL. The samples were irradiated at a temperature of ~450°C to 6.7 dpa. The results show the variation in size and number density of the Cr rich clusters and displacement defects as a function of Cr content, and help in understanding the behaviour of these alloys under neutron irradiation in different conditions by providing data for comparison with corresponding results from a previous series of the same alloys irradiated at ~320°C to ~1.8 dpa. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Phase Transformations, Iron and Steel |