About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Development of an IASCC Resistant 316L ODS Alloy for LWR Core Internals |
| Author(s) |
Arpan Arora, Satyavan P. Digole, Tushar M. Borkar, Stephen Raiman |
| On-Site Speaker (Planned) |
Arpan Arora |
| Abstract Scope |
This study focuses on the development of oxide dispersion-strengthened (ODS) 316L austenitic stainless steels for light water reactors (LWR). Three compositions of 316L ODS alloys were synthesized by mechanical alloying and consolidated using spark plasma sintering (SPS), incorporating 0.5, 1.0, and 2.0 wt.% Y₂O₃ as strengthening dispersoids. All samples were sintered at 1000 °C under an applied pressure of 60 MPa. The incorporation of Y₂O₃ resulted in significant grain refinement, achieving submicron grain sizes (<1 µm) with uniformly distributed nano-oxides throughout the matrix. Detailed microstructural characterization confirmed homogeneous dispersion of Y–O nanoparticles that effectively restricted grain boundary motion during sintering. Mechanical testing at 320 °C, representative of typical LWR operating conditions, revealed that all ODS alloys exhibited enhanced strength and structural stability compared to conventional 316L stainless steel. The improved performance was attributed to grain refinement and Orowan strengthening mechanisms imparted by the fine oxide dispersion. These findings underscore the potential of SPS-processed 316L ODS steels as promising candidates for advanced structural components in LWR systems. |
| Proceedings Inclusion? |
Undecided |