| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
An Investigation of FCCI Using Diffusion Couple Test between UMTZ Alloys and Cladding |
| Author(s) |
Weiqian Zhuo, Huali Wu, Michael T Benson, Jinsuo Zhang |
| On-Site Speaker (Planned) |
Weiqian Zhuo |
| Abstract Scope |
Two U-rich alloys containing additives Mo, Ti, Zr are proposed as fuel candidates, the alloys are U-1.5Mo-1.5Ti-7Zr (UMT7Z), and U-2.5Mo-2.5Ti-5Zr (UMT5Z) in wt.%. To investigate their fuel-cladding chemical interactions (FCCIs), the diffusion couple tests were performed between the fuel alloys and the cladding at 600℃. The as-cast fuel alloys and the pre-annealed alloys (annealed at 600C for 168h) were used for comparison because their microstructures and phases were different according to the scanning electron microscope (SEM) characterizations. The cladding materials were Fe and HT9. In those diffusion couples using as-cast alloys, Zr-rind was found at the fuel interfaces. The reaction product UFe2 was found at the HT9 side but not at the Fe side. The interface interaction of those diffusion couples using pre-annealed alloys is expected to be different from that of the as-cast alloys. |
| Proceedings Inclusion? |
Undecided |