Study Reveals Three-Dimensional Pore Networks Inside Uranium-Zirconium Metallic Nuclear Fuel
Researchers at the Massachusetts Institute of Technology (MIT), in collaboration with Idaho National Laboratory (INL), conducted three-dimensional imaging studies on irradiated uranium-10 zirconium metallic fuel, revealing the internal pore networks within the fuel and their relationship with chemical changes and fuel-cladding interactions. The researchers believe these results will help improve metallic fuel performance models, providing references for extending the operating cycles of certain reactors and for the design of next-generation sodium-cooled fast reactor fuel systems. Uranium-10 zirconium (U-10Zr) is a uranium-zirconium alloy metallic fuel containing 10% zirconium, which has been extensively tested in sodium-cooled fast reactors such as Experimental Breeder Reactor II (EBR-II) and the Fast Flux Test Facility (FFTF). As advanced reactor research and development progresses, this type of metallic fuel has regained attention, but the details of pore formation, swelling, heat transfer, and interactions with cladding materials under reactor irradiation conditions still require further clarification.
2026-08-13
