About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
|
Symposium
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Materials and Chemistry for Molten Salt Systems
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Presentation Title |
Impurity and Corrosion Assessment in Purified Molten Fuel NaF-BeF₂-UF₄-ZrF₄ Salts |
Author(s) |
Amanda Leong, Matthew Si, Jaewoo Park, Trevor Bradshaw, Xander Hromiak, Jinsuo Zhang |
On-Site Speaker (Planned) |
Amanda Leong |
Abstract Scope |
Molten salt reactors (MSRs) offer a promising approach to nuclear energy production. Impurities such as oxides, moisture, and sulfides can significantly impact the redox potential in molten salt environments. To address this, a fuel salt purification system was developed to reduce these impurities through thermal, chemical, and physical separation. Analytical techniques like combustion analysis, inert gas fusion analysis, and Inductively Coupled Plasma Mass Spectrometry (ICP-MS) were used to assess impurity levels of remaining metals, oxygen, hydrogen, carbon, and sulfur in purified salts, providing essential insights for purification process optimization. Preliminary corrosion tests using SS316 in purified salts revealed that an average of 272 ± 78.5 ppm of oxygen resulted in minimal degradation, with a maximum attack depth of 5 μm after 100 hours at 704°C in NaF-BeF₂-UF₄-ZrF₄. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Environmental Effects |