NSUF 19-1782: Scanning/Transmission Electron Microscopy Characterization of Irradiated Zr-1Nb-O During Thermal Treatments

The niobium, an alloying element in zirconium alloys, improves the radiation damage tolerance during nuclear reactor operation. The knowledge of the irradiation-induced microstructural evolution of β-Nb precipitates in neutron-irradiated nuclear fuel cladding of Zr-1Nb-O is limited. In this research, we propose a TEM study on the effect of neutron-irradiation on β-Nb precipitates to explain the how β-Nb microstructure evolves in the oxide layer, metal-oxide interface, and metal regions of high-burn up Zr-1Nb-O alloy nuclear fuel rod cladding. The sample is available at INL’s Hot Fuel Examination Facility. Microstructural characterization will be performed using the FEI Talos S/TEM optimized for elemental characterization. S/TEM with EDX will be conducted to determine β-Nb microstructure, Nb chemistry, dislocation structure and irradiation-induced features evolved during irradiation. The acquired data will enable a greater understanding of how Nb microstructure is affected in Zr-Nb-O alloy system at high burnups

Additional Info

Field	Value
Awarded Institution	Oak Ridge National Laboratory
Embargo End Date	2026-02-27
Facility Tech Lead	Alina Montrose, Kory Linton
NSUF Call	FY 2019 RTE 2nd Call
PI	Mahmut Cinbiz
PIE Facilities	Hot Fuel Examination Facility, Irradiated Materials Characterization Laboratory
Project Member	Dr. Mahmut Cinbiz - Oak Ridge National Laboratory (https://orcid.org/0000-0003-4626-8515)
Project Notes	Awarded on 05/14/2019
Project Type	RTE
RTE Number	1782