Development of Improved Sorbents for Radiochemical Separations at the SRS

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High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90 and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for Cs-137 removal, and ion exchange/sorption of Sr-90 and alpha-emitting radionuclides with monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239 and Pu-240. This paper describes results from a project funded by the U.S. Department of Energy Office of Cleanup Technology to produce sorbents that exhibit increased removal kinetics and capacity for Sr-90 ... continued below

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HOBBS, DAVID January 20, 2005.

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High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90 and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for Cs-137 removal, and ion exchange/sorption of Sr-90 and alpha-emitting radionuclides with monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239 and Pu-240. This paper describes results from a project funded by the U.S. Department of Energy Office of Cleanup Technology to produce sorbents that exhibit increased removal kinetics and capacity for Sr-90 and alpha-emitting radionuclides versus that of the baseline MST material. Testing indicated that MST samples prepared in the presence of organic-based templating reagents showed limited improvements in performance compared to the baseline MST. We observed significantly improved plutonium and neptunium removal performance with MST samples prepared upon the addition of a proprietary reagent. The modified MST offers the possibility of increased throughput and reduced solids handling in waste processing facilities at the SRS.

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  • Report No.: WSRC-MS-2004-00647R1
  • Grant Number: DE-AC09-96SR18500
  • Office of Scientific & Technical Information Report Number: 890075
  • Archival Resource Key: ark:/67531/metadc883638

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  • January 20, 2005

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  • Sept. 21, 2016, 2:29 a.m.

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  • Dec. 12, 2016, 3:38 p.m.

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HOBBS, DAVID. Development of Improved Sorbents for Radiochemical Separations at the SRS, article, January 20, 2005; [Aiken, South Carolina]. (digital.library.unt.edu/ark:/67531/metadc883638/: accessed August 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.