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Radiochemical Separations for the Pretreatment of High-Level Nuclear Waste Solutions at the Savannah River Site

[+] Author Affiliations
D. T. Hobbs, T. B. Peters, M. C. Duff, M. J. Barnes, S. D. Fink, D. D. Walker

Westinghouse Savannah River Company, Aiken, SC

Paper No. ICEM2003-4536, pp. 171-176; 6 pages
  • ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
  • 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
  • Oxford, England, September 21–25, 2003
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 0-7918-3732-7 | eISBN: 0-7918-3731-9
  • Copyright © 2003 by ASME


A significant fraction of the high-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) must be pretreated to remove 137 Cs, 90 Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at the SRS include caustic side solvent extraction for 137 Cs and sorption onto monosodium titanate (MST) for 90 Sr and alpha-emitters. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes 238 Pu, 239 Pu and 240 Pu. This paper describes the planned Sr/actinide separation process and summarizes recent tests and demonstrations with simulated and actual tank waste solutions.

Copyright © 2003 by ASME



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