Abstract
A significant reduction in and a change in the character of fuel-cladding chemical interaction (FCCI) due to a reduction in the oxygen-to-metal ratio (O/M) was established for uranium-plutonium mixed-oxide fuels clad with 20% cold-worked Type 316 stainless steel irradiated in the Experimental Breeder Reactor II. Fuel pins from the Hanford Engineering Development Laboratory P-23C subassembly at initial fuel O/Ms of 1.94, 1.95, and 1.97 were examined at peak burnups of 1.1, 2.5, and 3.6 at.%. The depth of FCCI increased with increasing burnup and temperature, but the relative effects of fuel O/M did not change. An approximate three-fold reduction in FCCI resulted from a reduction in fuel O/M from 1.97 to 1.95 at ~3.6 at.%) burnup. The peak FCCI in the lower O/M fuel was ~5 μm and appeared as a preferential loss of cladding at grain boundaries and slip planes on the cladding inner surface. In contrast, the typical FCCI in the higher O/M (1.97) fuel pin was matrix in character, and penetrated ~14 μm into the cladding. Thus, FCCI in mixed-oxide fuel can be reduced to negligible levels by lowering the O/M during manufacture of the fuel.
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.