About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials and Chemistry for Molten Salt Systems
|
Presentation Title |
O-7:The Reduction of Solid Uranium Dioxide in Calcium Salt |
Author(s) |
Nagihan Karakaya, Jinsuo Zhang |
On-Site Speaker (Planned) |
Nagihan Karakaya |
Abstract Scope |
Reprocessing the spent nuclear fuel has excessive attention due to reducing the radiotoxicity and increasing the efficiency of fuel utilization all around the world. The widely used nuclear fuel which is UO2 needs to be treated to convert into the metal form to further processing to obtain a new form of nuclear fuel.
In this study, the oxide reduction mechanisms of solid UO2 were investigated in two separate categories; -Chemical reduction and -Electrochemical reduction in calcium salts. In chemical reduction, the concentration effect of active metal (Ca) was determined under various applications. In electrochemical experiments, the temperature effects were determined on the reduced uranium metal. And the clear comparisons between the two methods have been determined by examining the samples under SEM-EDS and XRD analyses. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Recycling and Secondary Recovery, Sustainability |