Assessment of Active Metal Removal from Pyroprocessing Salt by Electrodeposition

Technical Report · Mon Jun 30 00:00:00 EDT 2025

DOI:https://doi.org/10.2172/2572438· OSTI ID:2572438

Gardner, L. ^[1]; Lichtenstein, T. ^[1]; Rose, M. A. ^[1]

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1. Argonne National Laboratory (ANL), Argonne, IL (United States)

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 ¹³⁷Cs and ⁹⁰Sr 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.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 2572438
• Report Number(s): ANL-CFCT--25-9; 197499
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY