Abstract
The Mk IV electrorefiner (ER) at Idaho National Laboratory has recovered uranium metal from used nuclear fuels for 27 years. Thus, large quantities of fission product chlorides more electropositive than uranium have accumulated in the ER salt, increasing the complexity of phase equilibria and salt speciation. Importantly, the melt temperature of the salt increases with ER operation and will ultimately exceed design limits without intervention. Methods to remove fission products from molten chloride salt are known, but their implementation at scale is not yet demonstrated. In this work, historical ER composition and differential scanning calorimetry (DSC) are utilized to develop coupled speciation and chloride salt solution thermochemistry models, which enable accurate present-day analysis of ER salt as well as forecast its future disposition. The developed thermochemical models are applicable to chloride salts generally and have been made available in the Molten Salt Thermal Properties Database – Thermochemical.
Original language | English |
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State | Published - 2024 |
Event | 153rd Annual Meeting and Exhibition of The Minerals, Metals and Materials Society, TMS 2024 - Orlando, United States Duration: Mar 3 2024 → Mar 7 2024 |
Conference
Conference | 153rd Annual Meeting and Exhibition of The Minerals, Metals and Materials Society, TMS 2024 |
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Country/Territory | United States |
City | Orlando |
Period | 03/3/24 → 03/7/24 |
Keywords
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS
- MSTDB-TC
- Thermal measurements
- Electrorefining
- EBR-II
- Thermodynamic assessment
INL Publication Number
- INL/CON-24-76838
- 170043