|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Comparison of Zirconium Oxidation Behavior under Oxygen-rich Gaseous and High Humidity Environments via In-situ TEM
||Wayne Harlow, Mitra L. Taheri
|On-Site Speaker (Planned)
Zirconium-based alloys are commonly used for nuclear fuel rod cladding material because of their good oxidation resistance and low neutron cross section. While long-term oxidation behavior has been studied through both reactor and autoclave oxidized samples, first stage oxidation has not been extensively studied. To investigate early stages of oxidation, a Protochips™ environmental holder was used to oxidize samples inside the TEM. Oxidation experiments were performed in-situ at elevated temperature under a 50% oxygen 50% argon gas atmosphere, and under a high humidity atmosphere to more closely replicate a steam environment. Precession diffraction techniques were used to identify the oxide phases formed, as well as the orientation of the oxide grains. In addition, the phase stability of stress-stabilized tetragonal ZrO2 versus monoclinic ZrO2 was studied. By studying first stage oxidation behavior, it is possible that improvements to oxidation behavior may be made through alloying additions or thermomechanical processing.
||Planned: A print-only volume