About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Enhancing Performance of LWR Control Rods by Cr Coating Deposition |
| Author(s) |
Evan J. Willing, Katsuri Sasidhar, Bennett LaSalle, Wen-Yo Yen, Noah Anderson, Hwasung Yeom, Kumar Sridharan |
| On-Site Speaker (Planned) |
Evan J. Willing |
| Abstract Scope |
Control rods regulate the fission rate in light water reactors (LWRs). In event of an accident, the current stainless steel control rod sheaths can be susceptible to high temperature steam oxidation and interdiffusion between the sheath and Zr alloy guide tube leading to Zr-Fe eutectic melting. Chromium coatings on the sheath can provide an oxidation resistant surface while also serving as a diffusion barrier between the sheath and the guide tube. Tests performed in 1200o C steam environment showed that the Cr coatings deposited on 300-grade austenitic stainless steel by cold spray deposition and PVD methods led to enhancement in oxidation resistance. Results of diffusion couple studies between Cr-coated and uncoated stainless steel and Zr-alloy in the temperature range of 900o C to 1200o C will also be presented. Interdiffusion and phase formation were investigated using x-ray diffraction and cross-sectional SEM-EDS/EBSD methods, and supported by CALPHAD-based models. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Surface Modification and Coatings |