Demonstration of a SREX flowsheet for the partitioning of strontium and lead from actual ICPP sodium-bearing waste

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Laboratory experimentation has indicated that the SREX process is effective for partitioning {sup 90}Sr and Pb from acidic radioactive waste solutions located at the Idaho Chemical Processing Plant. Previous countercurrent flowsheet testing of the SREX process with simulated waste resulted in 99.98% removal of Sr and 99.9% removal of Pb. Based on the results of these studies, a demonstration of the SREX flowsheet was performed. The demonstration consisted of (1) countercurrent flowsheet testing of the SREX process using simulated sodium-bearing waste spiked with {sup 85}Sr and (2) countercurrent flowsheet testing of the SREX process using actual waste from tank WM-183. ... continued below

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36 p.

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Law, J. D.; Wood, D. J.; Olson, L. G. & Todd, T. A. August 1, 1997.

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Laboratory experimentation has indicated that the SREX process is effective for partitioning {sup 90}Sr and Pb from acidic radioactive waste solutions located at the Idaho Chemical Processing Plant. Previous countercurrent flowsheet testing of the SREX process with simulated waste resulted in 99.98% removal of Sr and 99.9% removal of Pb. Based on the results of these studies, a demonstration of the SREX flowsheet was performed. The demonstration consisted of (1) countercurrent flowsheet testing of the SREX process using simulated sodium-bearing waste spiked with {sup 85}Sr and (2) countercurrent flowsheet testing of the SREX process using actual waste from tank WM-183. All testing was performed using 24 stages of 2-cm diameter centrifugal contactors which are installed in the Remote Analytical Laboratory hot cell. The flowsheet tested consisted of an extraction section (0. 15 M 4`,4`(5)-di-(tert-butyldicyclohexo)-18-crown-6 and 1.5 M TBP in Isopar-L{reg_sign}), a 2.0 MHNO{sub 3} scrub section to remove extracted K from the SREX solvent, a 0.05 M HNO{sub 3} strip section for the removal of Sr from the SREX solvent, a 0.1 M ammonium citrate strip section for the removal of Pb from the SREX solvent, and a 3.0 M HNO{sub 3} equilibration section. The behavior of {sup 90}Sr, Pb, Na, K, Hg, H{sup +}, the actinides, and numerous other non-radioactive elements was evaluated. The described flowsheet successfully extracted and selectively stripped Sr and Ph from the SBW simulant and the actual tank waste. For the testing with actual tank waste (WM - 183), removal efficiencies of 99.995 % and >94% were obtained for {sup 90}Sr and Pb, respectively.

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36 p.

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INIS; OSTI as DE98050368

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  • Other Information: PBD: Aug 1997

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  • Other: DE98050368
  • Report No.: INEEL/EXT--97-00832
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/568712 | External Link
  • Office of Scientific & Technical Information Report Number: 568712
  • Archival Resource Key: ark:/67531/metadc696970

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

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  • August 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 25, 2016, 11:36 a.m.

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Law, J. D.; Wood, D. J.; Olson, L. G. & Todd, T. A. Demonstration of a SREX flowsheet for the partitioning of strontium and lead from actual ICPP sodium-bearing waste, report, August 1, 1997; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc696970/: accessed October 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.