About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials and Chemistry for Molten Salt Systems
|
Presentation Title |
Redox Measurement and Control in Molten Chloride Fast Reactor Fuel Salt |
Author(s) |
Matthew Newton, D. Ethan Hamilton, Michael F. Simpson |
On-Site Speaker (Planned) |
Matthew Newton |
Abstract Scope |
One problematic issue with molten salt reactors (MSRs) is the tendency for redox potentials of salts to increase with irradiation, causing greater salt corrosivity. Na, Ca, U, and Zr were identified as redox buffer candidates in a NaCl-CaCl2-UCl3 salt. Redox potentials—represented by open circuit potential (OCP)—were measured at a tungsten working electrode vs. a Ag/AgCl reference electrode housed in a mullite tube. Continuous OCP measurements were taken at 600°C while NiCl2 was added to the molten salt to replicate irradiation effects on redox potential. OCP rose by 0.23 V with the addition of NiCl2. A zirconium rod was submerged in the salt, causing an OCP drop of -0.63 V over 100 minutes. Results for U, Na, or Ca redox buffers will also be presented. Uranium and zirconium are promising redox buffers since they neither dissolve in the salt nor reduce the potential below sustainable operating conditions for MSRs. |
Proceedings Inclusion? |
Planned: |