Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte
Abstract
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.
- Inventors:
-
- Batavia, IL
- Issue Date:
- Research Org.:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 989498
- Patent Number(s):
- 7799185
- Application Number:
- 11/530,573
- Assignee:
- The United States of America as represented by the United States Department of Energy (Washington, DC)
- Patent Classifications (CPCs):
-
C - CHEMISTRY C25 - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES C25C - PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS
- DOE Contract Number:
- W-31-109-ENG-38
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
Citation Formats
Willit, James L. Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte. United States: N. p., 2010.
Web.
Willit, James L. Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte. United States.
Willit, James L. Tue .
"Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte". United States. https://www.osti.gov/servlets/purl/989498.
@article{osti_989498,
title = {Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte},
author = {Willit, James L},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Sep 21 00:00:00 EDT 2010},
month = {Tue Sep 21 00:00:00 EDT 2010}
}