About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Biaxial Irradiation Creep Deformation of HT9 From 360°C-600°C: Experimental Results and Deformation Analysis |
| Author(s) |
Nathan J. Beets, Andrew Peterson, Greg Vetterick |
| On-Site Speaker (Planned) |
Nathan J. Beets |
| Abstract Scope |
Ferritic-martensitic (FM) steels are the most attractive material for sodium-cooled fast reactor cladding due to their corrosion and creep resistance, and resistance to irradiation swelling. Understanding the creep performance of FM steels under an actively irradiated environment is critical for component design and lifetime prediction. Knowing how the dominant deformation mode changes as a function of temperature and applied stress for a component under irradiation can help set conservative design limits to maximize both performance and safety. In this work, the results of irradiation creep experiments performed at the BOR-60 test reactor on pressurized/welded TerraPower HT9 tube samples will be presented. Strain measurements of irradiated specimens have been statistically analyzed and an empirical model of creep deformation has been fit accounting for separate contributions from thermal creep, irradiation creep, and irradiation-induced swelling. The results will be compared to thermal creep deformation experiments on both TerraPower HT9 and published HT9 thermal creep results. The data will also be evaluated against pressurized irradiation creep deformation experiments from the literature. Anomalous creep performance has been observed over a limited temperature range, which will be analyzed. The results and analysis presented build a greater understanding of the evolution of irradiation creep properties in FM steels, and how creep response evolves relative to applied temperature and stress. |
| Proceedings Inclusion? |
Undecided |