|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||Oxidation of FeCrAl Alloys in Simulated PWR Environments during In-situ Proton Irradiation
||Peng Wang, Gary S. Was
|On-Site Speaker (Planned)
Following the high oxidation rate of fuel rods during the Fukushima Daiichi nuclear accident in 2011, the emphasis for nuclear fuel R&D activities has shifted to the development of accident-tolerance of LWR fuel. FeCrAl alloys were selected as one of the candidate materials for Accident-Tolerant Fuel application due to their excellent high temperature (1200˚C) corrosion resistance in steam. Corrosion experiments on 30 µm thick FeCrAl alloy samples were conducted in high purity water at 320˚C containing 3 appm H2 during irradiation with 3.2 MeV protons to evaluate the effect of irradiation on the corrosion behavior. The thin sample acts as a “window” to allow protons to fully penetrate and deposit their energy in water to induce radiolysis while creating displacement damage in the metal. Results of oxide film characterization via TEM and Raman spectroscopy will be combined data on corrosion rate to determine the effect of irradiation on corrosion.
||Planned: A print-only volume