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Electrolytic Recycling of a Carbonate Salt in a Process With a Dissolution of Spent Nuclear Fuel in a Strong Alkaline Carbonate Media

[+] Author Affiliations
Kwang-Wook Kim, In-Tae Kim, Seong-Min Kim, Yeon-Hwa Kim, Eil-Hee Lee, Kwang-Yong Jee

Korea Atomic Energy Research Institute, Daejeon, South Korea

Paper No. ICEM2007-7327, pp. 789-793; 5 pages
  • The 11th International Conference on Environmental Remediation and Radioactive Waste Management
  • 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B
  • Bruges, Belgium, September 2–6, 2007
  • Conference Sponsors: Nuclear Division and Environmental Engineering Division
  • ISBN: 978-0-7918-4339-0 | eISBN: 0-7918-3818-8
  • Copyright © 2007 by ASME


A removal of only uranium from spent nuclear fuel with the concepts of a high proliferation-resistance and a minimal generation of waste is helpful for a spent fuel management in view of a volume reduction of the high level radioactive waste generated from the spent fuel treatment. That can be accomplished by a process using a selective oxidative dissolution of the spent fuel in a carbonate solution of high alkalinity. In this work, an electrolytic method for a decarbonation and a recovery of CO2 for recycling the used carbonate solution contaminated with some impurity metal ions generated in such a process with a concept of zero-release of waste solution was studied. A carbonate solution generated from such a system was confirmed to be completely recycled within the system, while the impurity ions being separated from the carbonate solution.

Copyright © 2007 by ASME



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