About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials and Chemistry for Molten Salt Systems
|
Presentation Title |
N-11: Methods for Recycle of Uranium in Molten Salt Reactor Fuel |
Author(s) |
Claire Perhach |
On-Site Speaker (Planned) |
Claire Perhach |
Abstract Scope |
For the purpose of generating UCl3 in fuel salt for a molten salt reactor (MSR), bubbling HCl into the molten salt in contact with U metal was investigated. The base salt used for this study was equimolar NaCl-CaCl2. First the NaCl-CaCl2 was purified via heating to 200°C and purified by bubbling 10% HCl gas balanced with argon. Effluent gas was fed into an auto-titrator which measured the consumption of HCl in real time and was used to determine when to stop the reaction. Then, a uranium rod (3” by 2.1mm) was inserted into salt while 10% HCl gas balanced with argon was bubbled in. Salt samples were taken and analyzed for U concentration using inductively coupled plasma mass spectrometry (ICP-MS). Applicability of this process to an integrated MSR fuel processing scheme that includes actinide drawdown from waste salt and dechlorination of waste salt will be discussed. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Pyrometallurgy, Recycling and Secondary Recovery |