About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials and Chemistry for Molten Salt Systems
|
Presentation Title |
Design of Molten Salt Static Corrosion Experiments to Predict Phenomena Relevant to Corrosion in Non-isothermal Nuclear Reactor Salt Loops |
Author(s) |
Raluca Scarlat |
On-Site Speaker (Planned) |
Raluca Scarlat |
Abstract Scope |
Corrosion of metal alloys in the salt loops of a molten salt (MSR) or a salt-cooled nuclear reactors (FHR) is continuously driven by the presence of a thermal gradient coupled with mass convection. This system-level driving force creates a local thermodynamic driver for corrosion of metal piping and components. The question of whether similar corrosion conditions can be generated in static corrosion capsules will be discussed. Fission and neutron activation reactions, and inadvertent ingress of materials into the coolant can have an oxidizing effect on the salt and are another driver of corrosion, which is generally mitigated by redox control. How these effects could or should be replicated in static corrosion capsules will be discussed. Examples of redox control and redox measurements will be demonstrated, and a discussion of the limitation of static corrosion capsules will be provided. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, High-Temperature Materials, |