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Initial results for electrochemical dissolution of spent EBR-II fuel [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1998.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
11 pages : digital, PDF file
Additional Creators
Argonne National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
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.
Report Numbers
E 1.99:anl/td/cp-96338
anl/td/cp-96338
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Note
Published through SciTech Connect.
05/04/1998.
"anl/td/cp-96338"
American Nuclear Society 3rd Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998.
Li, S. X.
Funding Information
W-31109-ENG-38
View MARC record | catkey: 14364479