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Study mapping U-10Zr porosity informs metallic fuel design
Researchers at Idaho National Laboratory and the Massachusetts Institute of Technology have conducted a three-dimensional study of irradiated U-10Zr—uranium alloyed with 10 percent zirconium—across key radial regions, providing new insights into how the material swells, transfers heat, and interacts with the fuel cladding.
U-10Zr was extensively tested in historical sodium-cooled fast reactors and is now attracting attention for use in next-generation advanced reactors.
Kenichi Tada (Japan Atomic Energy Agency), Ryoichi Kondo (Japan Atomic Energy Agency), Tomohiro Kamiya (Japan Atomic Energy Agency), Taku Nagatake (Japan Atomic Energy Agency), Ayako Ono (Japan Atomic Energy Agency), Yasunobu Nagaya (Japan Atomic Energy Agency), Hiroyuki Yoshida (Japan Atomic Energy Agency)
Proceedings | International Conference on Physics of Reactors (PHYSOR 2024) | San Francisco, CA, April 21-24, 2024 | Pages 1488-1497
