| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
|
| Presentation Title |
Material Characterization and Pellet Cladding Interaction Performance of Optimized ZIRLO™ with Liner |
| Author(s) |
Caleb Clement, Guirong Pan, Magnus Limback, Antoine Ambard, Zaheen Shah, Nermine Chaari-Schule, Kenneth Gorannsson, Britta Helmersson, Jonna Partezana, Julian Soulacroix |
| On-Site Speaker (Planned) |
Caleb Clement |
| Abstract Scope |
To facilitate an increased demand for load-following in French nuclear power plants, a lined cladding technology originally used in boiling-water reactor applications was developed for pressurized-water reactors. This Optimized ZIRLO™ with Liner (OZL) has shown through in-pile and out-of-pile testing to provide improved pellet cladding interaction (PCI) margin compared to unlined cladding.
This presentation discusses the comprehensive analysis of the OZL performance, including out-of-pile microstructural assessment, corrosion weight-gain assessment, secondary phase particle analysis, bi-axial creep, burst testing, fatigue testing, and microhardness testing. In-pile testing includes poolside oxide examination, hot cell creep testing, and power ramp testing of OZL at burnup up to 58MWd/kgU. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, |