| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
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| Symposium
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Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
Characterization and Modeling of Joint Oxyde-Gaine and Inner Cladding Corrosion in Fast Reactor Fuels |
| Author(s) |
Aurelien Hoel-Bacle, Jean-Christophe Dumas, Philippe Bienvenu, Karine Hanifi, Isabelle Zacharie-Aubrun, Thierry Blay, Ingrid Roure, Catherine Sabathier, Doris Drouan, Laurent Fayette, Nicolas Robert, Pierre Benigni, Charlotte S. Becquart |
| On-Site Speaker (Planned) |
Aurelien Hoel-Bacle |
| Abstract Scope |
Post-irradiation examinations (PIE) at the fuel-cladding interface of fast reactor fuels have revealed the formation of a volatile fission products layer, called JOG (for Joint Oxyde-Gaine), and the development of a corrosion process of the inner cladding through FCCI (Fuel Cladding Chemical Interaction). A JOG and FCCI model has been implemented by integrating the thermodynamic software OpenCalphad and the TAF-ID database into the GERMINAL fuel performance code, which aims to simulate the in-pile behavior of fast reactor fuel pins. Recently, destructive examinations of high burnup fast reactor fuel samples have been performed to improve our knowledge on the development of JOG and FCCI using Optical Microscopy, FIB-SEM, TEM, EPMA and SIMS. The purpose of the presentation is to discuss these new experimental results and compare them with the predictions of the thermochemical model. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Modeling and Simulation |