Demonstrates low-temperature uranium recovery in ionic liquids, implying reduced corrosion risk.
Dry reprocessing of spent nuclear fuel traditionally relies on high-temperature molten salts with high energy consumption and corrosion. Ionic liquids offer a promising low-temperature alternative due to their low melting points and wide electrochemical windows. Here, we use the room-temperature phosphonium ionic liquid tributylmethylphosphonium chloride ([P 1444 ]Cl) to electrodeposit and recover uranium as UO 2 . Quantum chemical calculations reveal that the [P 1444 ] + cation has a uniformly low surface electrostatic potential and weak P–Cl binding energy, explaining its liquid state at ambient temperature. Molecular dynamics simulations show that uranyl mainly forms UO 2 Cl 4 2– complexes. Electrochemical measurements indicate that the U(VI) → U(IV) reduction is an irreversible, diffusion-controlled two-electron process. Potentiostatic deposition at −1.3 to −2.0 V yields a dense amorphous UO 2 layer; after annealing, XRD confirms conversion to crystalline UO 2 . These findings demonstrate the feasibility of [P 1444 ]Cl for low-temperature, low-corrosion uranium recovery and provide insights into uranyl speciation and reduction in ionic liquid media.
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Jiang et al. (2026) studied this question.
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