| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
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| Presentation Title |
Numerical Modeling of AA6061 Cladding Diffusion Bonding for the U-10Mo Monolithic Fuel |
| Author(s) |
Yucheng Fu, Taylor Mason, Rajib Kalsar, Zhijie Xu, Kriston P Brooks, Ayoub Soulami, Vineet Joshi |
| On-Site Speaker (Planned) |
Yucheng Fu |
| Abstract Scope |
The low enriched U-10Mo alloy is a promising fuel candidate for United States high performance research reactors. The fuel is designed to be encapsulated in the aluminum alloy 6061 (AA6061) cladding, which is diffusion bonded using the hot isostatic pressing (HIP). The diffusion bonding promotes a homogeneous AA6061/AA6061 bonding interface, preventing fuel corrosion and fission product release. To optimize the bonding quality and reduce experimental cost, an integrated FEM-Diffusion model was developed to model the aluminum cladding diffusion bonding, which involves the interface void closures and the formation of Mg2Al2O5 due to the Mg/Al diffusion. Combined with sensitivity analysis, it was found that temperature was the most dominant factor compared to the HIP time and applied pressure. With HIP temperature over 400 ºC, the interface voids will fully collapse, and the aluminum cladding can reach a desirable bonding strength. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Computational Materials Science & Engineering, Aluminum |