|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Corrosion Studies on U-10Mo Fuel for Research Reactor Applications
||Ramprashad Prabhakaran, Levi Gardner, Vineet Joshi, Curt Lavender, Douglas Burkes
|On-Site Speaker (Planned)
Currently, efforts are ongoing to develop new nuclear fuels to enable research and test reactors to use low-enriched uranium fuel instead of high-enriched uranium fuel, without significant loss in performance. A new monolithic fuel type that possesses the greatest possible uranium density in the fuel region is being developed, where the fuel region consists of a single foil encased inside an aluminum alloy cladding. The corrosion behavior of low-enriched uranium-molybdenum (U-Mo) fuel in research reactor conditions is not available. Hence, efforts are ongoing to evaluate the corrosion behavior of U-10Mo fuel, using electrochemical and mass loss experiments, as a function of fabrication parameters, pH and temperature. The results of corrosion experiments along with the mechanical properties and microstructural analysis will be presented at the conference.
||Planned: A print-only volume