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DOE OSTI · 2572438

Assessment of Active Metal Removal from Pyroprocessing Salt by Electrodeposition

Gardner, L. [Argonne National Laboratory (ANL), Argonne, IL (United States)]·Lichtenstein, T. [Argonne National Laboratory (ANL), Argonne, IL (United States)] (ORCID:0000000247399907)·Rose, M. A. [Argonne National Laboratory (ANL), Argonne, IL (United States)]
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Abstract

Active metals present in used nuclear fuel dissolve into the salt during pyroprocessing, but are not recovered during electrorefining or drawdown operations due to their chemical stability in the salt. The accumulation of 137 Cs and 90 Sr in process salt over time increases the heat load and ionizing radiation level of the salt such that it must be replaced frequently, resulting in a significant amount of salt waste. An effective means of removing active metals from the molten salt to enable recycle of the electrolyte (e.g., LiCl/KCl) would increase the efficiency of pyroprocessing and decrease the volume of salt waste requiring disposal.

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY

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BibTeXRIS

Gardner, L. [Argonne National Laboratory (ANL), Argonne, IL (United States)], Lichtenstein, T. [Argonne National Laboratory (ANL), Argonne, IL (United States)] (ORCID:0000000247399907), Rose, M. A. [Argonne National Laboratory (ANL), Argonne, IL (United States)]. 2025-06-30. Assessment of Active Metal Removal from Pyroprocessing Salt by Electrodeposition. https://doi.org/10.2172/2572438

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