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Original Articles

Separation and Recovery of Uranium and Group Actinide Products From Irradiated Fast Reactor MOX Fuel via Electrolytic Reduction and Electrorefining

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Pages 2044-2059 | Received 19 Oct 2011, Accepted 18 Apr 2012, Published online: 02 Nov 2012

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Steven D. Herrmann, Brian R. Westphal, Shelly X. Li & Haiyan Zhao. (2022) Parametric Study of Used Nuclear Oxide Fuel Constituent Dissolution in Molten LiCl-KCl-UCl3. Nuclear Technology 208:5, pages 871-891.
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