About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
Dependence of grain boundary structure on radiation induced segregation and tritium distribution in coated 316 stainless steel cladding |
| Author(s) |
Francelia Sanchez, Semanti Mukhopadhyay, Dallin Barton, Jaqueline Royer, Kayla Yano, Jenna Pope, Arun Devaraj |
| On-Site Speaker (Planned) |
Francelia Sanchez |
| Abstract Scope |
316 Austenitic stainless steel (SS) is used as the cladding for tritium producing burnable absorber rods due to its elevated corrosion resistance and high-temperature strength. Nonetheless, the material is susceptible to radiation induced segregation (RIS) to defect sinks such as grain boundaries (GB). These changes in elemental distribution may alter the hydrogen solubility and hydrogen diffusion in 316 SS. In the present study, the effect of neutron irradiation on the RIS to special and random high angle GB of a 316SS cladding is investigated to elucidate the dependence of GB characteristics on tritium diffusion. The GB character of the material was analyzed using electron backscatter diffraction. The cross-sectional microstructure and elemental distribution of special and random high angle grain boundaries were investigated using scanning transmission microscopy with energy dispersive X-ray spectroscopy. Further, the elemental segregation at the GB before and after neutron irradiation was revealed by atom probe tomography analysis. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Iron and Steel, Nuclear Materials |