About this Abstract |
| Meeting |
MS&T25: Materials Science & Technology
|
| Symposium
|
Metallic Nuclear Fuel Design, Fabrication and Characterization
|
| Presentation Title |
Metal Fuel Performance in Sodium Fast Reactors: Post-Irradiation Examination and Innovative Experiments |
| Author(s) |
Tiankai Yao |
| On-Site Speaker (Planned) |
Tiankai Yao |
| Abstract Scope |
The United States Department of Energy (DOE) has extensive experience in developing sodium-cooled fast reactors, as demonstrated by the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF). Metal fuels were tested under both steady-state and off-normal reactor conditions. To address the increasing industry needs for metal fuel qualification, the DOE's Office of Nuclear Energy Advanced Fuel Campaign program is supporting post-irradiation examination (PIE) and post-testing characterization of irradiated metal fuel specimens from EBR-II and FFTF. This presentation will discuss our progress in these areas as well as new irradiation experiments conducted at the Transient Reactor Test Facility (TREAT) and the Advanced Test Reactor (ATR). |