DOE OSTI · 1978545
Zirconium nanoparticle coating development for FCCI diffusion barrier in nuclear cladding
Abstract
Fuel clad chemical interaction (FCCI) is a pervasive issue for metallic nuclear fuels. FCCI can damage cladding, reduce thermal efficiency, and compromise the structural integrity of the fuel rod. In this study, we evaluated the FCCI mitigation capabilities of electrophoretically-deposited Zr nanoparticle coatings on ferritic-martensitic stainless-steel cladding (HT9). Zr was deposited on the internal surface of 6 mm outer diameter cladding using electrophoretic deposition (EPD). Thickness varied among samples with similar EPD conditions. A uniformly coated sample was selected and sent to the Argonne Tandem Linac Accelerator System (ATLAS) to simulate the coating's behavior under irradiation conditions. Furthermore, the coating prevented FCCI in diffusion couple studies. Results of this study confirm that Zr could potentially make an effective FCCI barrier in metallic fuel rods but the deposition process needs improvement.
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Hamilton, Sarah, Childs, Mason, Bhattacharya, Sumit, Yacout, Abdellatif, Moceri, Matteo, Sudderth, Laura. 2023-04-24. Zirconium nanoparticle coating development for FCCI diffusion barrier in nuclear cladding. https://doi.org/10.1016/j.surfcoat.2023.129501
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