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Title: 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:
 [1]
  1. Ratavia, IL
Publication Date:
Research Org.:
Argonne National Laboratory (ANL), Argonne, IL
Sponsoring Org.:
USDOE
OSTI Identifier:
914625
Patent Number(s):
7,267,754
Application Number:
10/761,916
Assignee:
U.S. Department of Energy (Washington, DC) CHO
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Willit, James L. Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte. United States: N. p., 2007. 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/914625.
@article{osti_914625,
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 = {2007},
month = {9}
}

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