NEUP CINR-24-31764: Comparative study of three-dimensional microstructural imaging and thermal conductivity evolution of irradiated solid and annular U-Zr fuels

Uranium-zirconium (U-Zr) annular metallic fuel holds the promise to simultaneously increase sodium fast reactor (SFR) core uranium loading and reduce peak cladding temperatures, thus greatly improving fuel performance. However, key convolved fuel degradation mechanisms during irradiation at temperature threaten to hold back its real-world applicability, requiring more detailed understanding to both predict U-Zr fuel performance and suggest improvements.

Additional Info

Field	Value
Awarded Institution	Massachusetts Institute of Technology
PI	Ericmoore Jossou