The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study

• Published in: Journal of nuclear materials 2024-04, Vol.591, p.154928, Article 154928
• Main Authors: Salvato, Daniele, Paaren, Kyle M., Hirschhorn, Jacob A., Aagesen, Larry K., Xu, Fei, Di Lemma, Fidelma Giulia, Capriotti, Luca, Yao, Tiankai
• Format: Article
• Language: English
• Subjects: BISON simulations; EDS; energy dispersive x-ray spectroscopy; FCCI; Fuel-cladding chemical interaction; HT-9 cladding; Metallic fuel; NUCLEAR FUEL CYCLE AND FUEL MATERIALS; scanning electron microscopy; SEM; U-Zr fuel
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2024.154928

The fuel cladding chemical interaction (FCCI) between Uranium-Zirconium-based metallic fuel and cladding materials during in-pile service is one of the most constraining phenomena affecting the performance of this fuel system. In this study, we investigated the effect of temperature and burnup on the FCCI development in two U-10 wt.% Zr (U-10Zr) fuel samples with HT-9 cladding irradiated as part of the MFF-3 irradiation test in the Fast Flux Test Facility (FFTF). One sample achieved a burnup of 13.1 at.% and operated with an average inner cladding temperature of 530 °C, while the other achieved a burnup of 8.5 at.% and was subjected to an average inner cladding temperature of 615 °C. Automated scanning electron microscopy (SEM) back-scattered electron (BSE) imaging of entire fuel cross-sections and SEM energy dispersive x-ray spectroscopy (EDS) analysis on specific fuel-cladding interface regions successfully provided a comprehensive characterization of the depth and type of interaction happening under different irradiation conditions. Our analysis shows that FCCI development on both fuel and cladding side is strongly influenced by the inner cladding temperature and, to some extent, the formation and integrity of Zr-rich layers between the fuel and cladding, while the impact of burnup and power is negligible. Measured FCCI thicknesses were compared to BISON simulations using both an empirical model based upon legacy data from the Experimental Breeder Reactor II (EBR II) irradiations and a mechanistic model currently under development for the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, showing satisfactory agreement. Nonetheless, this comparison supports the need for additional microstructural characterization in intermediate ranges of temperature, power, and burnups in prototypic-length pins. [Display omitted]