Initial results for electrochemical dissolution of spent EBR-II fuel.

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Initial results are reported for the anode behavior of spent metallic nuclear fuel in an electrorefining process. The anode behavior has been characterized in terms of the initial spent fuel composition and the final composition of the residual cladding hulls. A variety of results have been obtained depending on the experimental conditions. Some of the process variables considered are average and maximum cell voltage, average and maximum anode voltage, amount of electrical charge passed (coulombs or amp-hours) during the experiment, and cell resistance. The main goal of the experiments has been the nearly complete dissolution of uranium with the retention ... continued below

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11 p.

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Li, S. X. May 4, 1998.

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Description

Initial results are reported for the anode behavior of spent metallic nuclear fuel in an electrorefining process. The anode behavior has been characterized in terms of the initial spent fuel composition and the final composition of the residual cladding hulls. A variety of results have been obtained depending on the experimental conditions. Some of the process variables considered are average and maximum cell voltage, average and maximum anode voltage, amount of electrical charge passed (coulombs or amp-hours) during the experiment, and cell resistance. The main goal of the experiments has been the nearly complete dissolution of uranium with the retention of zirconium and noble metal fission products in the cladding hulls. Analysis has shown that the most indicative parameters for determining an endpoint to the process, recognizing the stated goal, are the maximum anode voltage and the amount of electrical charge passed. For the initial experiments reported here, the best result obtained is greater than 98% uranium dissolution with approximately 50% zirconium retention. Noble metal fission product retention appears to be correlated with zirconium retention.

Physical Description

11 p.

Notes

INIS; OSTI as DE00010759

Medium: P; Size: 11 pages

Source

  • American Nuclear Society 3rd Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998

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  • Report No.: ANL/TD/CP-96338
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 10759
  • Archival Resource Key: ark:/67531/metadc628561

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • May 4, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 7:38 p.m.

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Li, S. X. Initial results for electrochemical dissolution of spent EBR-II fuel., article, May 4, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc628561/: accessed December 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.