| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Overview of the United States Molten Salt Reactor Program |
| Author(s) |
Patricia Paviet |
| On-Site Speaker (Planned) |
Patricia Paviet |
| Abstract Scope |
The Molten Salt Reactor program under DOE- NE is responsible of developing the technological foundations to enable MSRs for safe development, deployment and economical operations. A brief overview of the program will be presented with some examples such as 1) Determination of the thermal properties of fluoride and chloride molten salts which provide fundamental baseline data for modeling and simulation in support of reactor design, construction, operation; 2) Radionuclide release management; 3) Materials studies with the establishment of an in-situ, passive surrogate materials surveillance project, that allows the collection of information on material degradations as an important pathway in support of verification & validation as well as licensing of MSR reactor systems; and 4) Expansion of modeling & simulation capabilities for mechanistic source term analysis, as a critical element of reactor licensing, using a combination of MELCOR code assisted with the Nuclear Energy Advanced Modeling and Simulation tools. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Other |