Abstract
Zirconium (Zr), a potential candidate for preventing Fuel-Cladding Chemical Interaction, shows stable interdiffusion behavior between cladding and fuel materials. However, a 25 μm-thick Zr foil allows local inter-diffusion, due to defects generated during manufacturing. In this study, we investigate the use of a Zr thin film deposited on Zr foil for preventing local inter-diffusion. The diffusion behavior of the Zr thin film on Zr foil was investigated using misch metal (Ce: 75% and La: 25%) as fuel fission product, in order to effectively simulate nuclear fuel. While without the Zr barrier substantial inter-diffusion occurred at the interface between the ferritic/martensitic HT9 cladding material and misch metal, the Zr thin film on Zr foil exhibited excellent resistance to interdiffusion. The enhancement of the barrier ability of the Zr thin film on Zr foil was attributed to a lower amount of defects induced by the Zr thin film layer.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.