The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel

• Published in: Journal of nuclear materials Vol. 537
• Main Authors: Thomas, Jonova, Figueroa Bengoa, Alejandro, Nori, Sri Tapaswi, Ren, Ran, Kenesei, Peter, Almer, Jon, Hunter, James, Harp, Jason, Okuniewski, Maria A.
• Format: Journal Article
• Language: English
• Published: United States Elsevier 01-08-2020
• Subjects: metallic fuel; neutron irradiation; nuclear fuel; NUCLEAR FUEL CYCLE AND FUEL MATERIALS; porosity; swelling; synchrotron X-ray micro-computed tomography; U-10wt.%Zr
• ISSN: 0022-3115; 1873-4820

This research demonstrated the first time that synchrotron X-ray micro-computed tomography (μ-CT) was utilized to analyze the three-dimensional (3-D) morphology of the microstructure of irradiated nuclear fuel. Both absorption contrast and propagation-based phase contrast enhanced μ-CT techniques were evaluated. Porosity and phase region volumes were determined in neutron irradiated uranium 10 wt.% zirconium (U-10Zr) using propagation-based phase contrast enhanced μ-CT. Volumes were determined by image processing software and algorithms, with the porosity volume subsequently compared to the ASTM E562 method. The 3-D porosity of a small region (~ 8 x 105 µm3) located in the intermediate fuel redistribution zone that was removed via a focused ion beam was determined to be 7.2% via image processing. A detailed 3-D analysis of the porosity with respect to volume and morphology was provided. Five growth stages of pore evolution were observed including: nucleation, growth, coalescence, interconnected porosity, and extended/interconnected porosity. Four distinct phase regions were identified, including the pores, via both absorption contrast and propagation-based phase contrast enhanced μ-CT. A quantitative comparison of fuel swelling between this localized microscopic U-10Zr fuel region, previously irradiated in the Fast Flux Test Facility, and historic U-10Zr fuels irradiated in the Experimental Breeder Reactor-II (EBR-II) was conducted. It was determined that for similar burnups, the localized swelling in this microscopic fuel region was 7.7%, which was approximately one-half of the value of the macroscopic swelling reported in EBR-II irradiated fuel. With the advent of new specimen preparation tools for irradiated materials, as well as advances in characterization techniques, researchers can now obtain previously inaccessible microstructural insight into irradiated fuels. This possibility naturally lends itself to improved fuel performance models for the nuclear community.