Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte

Patent · Tue Sep 11 04:00:00 EDT 2007

OSTI ID:914625

Willit, James L ^[1]

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1. Ratavia, IL

An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL
• Sponsoring Organization: United States Department of Energy
• DOE Contract Number: W-31109-ENG-38
• Assignee: U.S. Department of Energy (Washington, DC)
• Patent Number(s): 7,267,754
• Application Number: 10/761,916
• OSTI ID: 914625
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS