| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Seaborg Institutes: Emerging Topics in Actinide Materials and Science
|
| Presentation Title |
Irradiation of Enriched Uranium Bearing Chloride Salt |
| Author(s) |
Abdalla Abou-Jaoude |
| On-Site Speaker (Planned) |
Abdalla Abou-Jaoude |
| Abstract Scope |
Idaho National Laboratory (INL) established an enriched uranium molten salt irradiation capability. Several private entities are pursuing Molten Salt Reactors (MSR) as a promising advanced nuclear technology. Understanding how molten salt (and wall material) behave in a reactor may be critical for the licensing and deployment of these concepts. INL demonstrated the capability to irradiate molten salt containing dissolved enriched uranium. The salt sample was UCL3-NaCl and the salt-wetted wall material was IN-625. This also marks the first time that fuel-bearing chloride salt has ever been irradiated in a reactor. In the longer term, the experiment is expected to provide insights on three key aspects of MSRs: (1) source term (quantifying radionuclide transport out of the salt), (2) corrosion (in the wall material), and (3) thermophysical property evolution under burnup. For the third objective, INL intends to leverage the Molten Salt Thermophysical Examination Capability (MSTEC) that is currently under development. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Copper / Nickel / Cobalt, Energy Conversion and Storage |