|About this Abstract
||Materials Science & Technology 2019
||Materials for Nuclear Applications
||In-situ Characterization of Zirconium Alloy Degradation to Support Nuclear Sensing Applications
||Michael Reynolds, Corey Michael Efaw, Samuel McMurdie, Pete Barnes, Hongqiang Hu, Claire Xiong, Michael F Hurley
|On-Site Speaker (Planned)
Degradation of nuclear fuel cladding remains an important area of research for reactor safety, efficiency, and longevity. Further, in-core monitoring of cladding degradation is needed to enable innovations in nuclear energy. Zirconium alloys provide a favorable cladding material because of their inherent corrosion resistance and low neutron cross-section. In-situ Raman spectroscopy and electrochemical impedance spectroscopy (EIS) were performed on zirconium alloys to observe oxide and hydride growth mechanisms. In-situ surface Raman supported by ex-situ cross-sectional mapping provided semi-quantitative crystallographic structure and associated stress development in the oxide formed at high temperatures. Through EIS, data correlating to oxide resistance and corrosion rate could be monitored as degradation evolved. Supported by Raman and other complementary characterization techniques, improved interpretation of the equivalent circuit components used to analyze EIS results was obtained. The techniques used in this work supports improved understanding of zirconium alloy degradation and development of in-core fuel cladding sensors.
||Definite: At-meeting proceedings