|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Strain Rate Sensitivity Studies of Commercial FeCrAl Alloy
||Hamdy Abouelella, Chengying Xu, Korukonda Linga Murty
|On-Site Speaker (Planned)
Since Fukushima nuclear accident in Japan 2011, FeCrAl Alloys have been considered as one of the accident tolerant fuel-cladding and structural materials for their superior oxidation resistance. While such oxidation process caused severe degradation in zirconium based clads at high temperatures, protective aluminum oxide layer in FeCrAl prevents further corrosion attack. Next-generation nuclear reactors are projected to work at higher operating temperatures and stresses. Therefore, the structural materials should have adequate mechanical properties that can withstand typical operating conditions expected in the nuclear reactor core. Since FeCrAl Alloy is a potential candidate as structural material to replace Zircaloys, the mechanical behavior of commercial FeCrAl Alloy is investigated at strain rates from 10^-3 to 10^-5 and at four different temperatures 550C,600C,650C,700C . Strain rate sensitivity parameter and the activation are evaluated for an understanding of the basic underlying deformation mechanism(s). This research is supported by DOE/NEUP project DE-NE0008874.
||Nuclear Materials, Mechanical Properties, High-Temperature Materials