|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Processbility Assessment of Accident-Tolerant FeCrAl Cladding Alloys
||Yukinori Yamamoto, Kevin G Field, Bruce A Pint, Kurt A Terrani
|On-Site Speaker (Planned)
Development of nuclear-grade wrought FeCrAl-base alloys is currently in progress which targets a new accident-tolerant fuel cladding substitute for current Zr-based alloys in light water reactors. Previous studies indicated that increasing the Cr and Al additions in the FeCrAl alloys enhances surface protection in high-temperature steam environments. However, excess amounts of Cr and Al make the FeCrAl alloys brittle which hinders use of the typical cold-forming process. Based on the tensile property evaluation, it was found that work hardening increases with additions of both Cr and Al in the range of Fe-(5-16)Cr-(3-8)Al-Y (wt.%) - with the Al addition ~five-times more potent than the Cr addition. Optimization of alloy composition is currently in progress to balance the oxidation resistance and the fabricability for making seamless tubes. Research funded by U.S. Department of Energy’s Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle R&D program.
||Planned: A print-only volume