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

Abstract

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,more » 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.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Idaho National Engineering Lab., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
OSTI Identifier:
568712
Report Number(s):
INEEL/EXT-97-00832
ON: DE98050368; TRN: 98:002520
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Aug 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; STRONTIUM 90; LEAD; ACTINIDES; NITRIC ACID; TBP; RADIOACTIVE WASTE PROCESSING; SIMULATION; IDAHO CHEMICAL PROCESSING PLANT; TANKS; SEPARATION PROCESSES

Citation Formats

Law, J D, Wood, D J, Olson, L G, and Todd, T A. Demonstration of a SREX flowsheet for the partitioning of strontium and lead from actual ICPP sodium-bearing waste. United States: N. p., 1997. Web. doi:10.2172/568712.
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. United States. doi:10.2172/568712.
Law, J D, Wood, D J, Olson, L G, and Todd, T A. Fri . "Demonstration of a SREX flowsheet for the partitioning of strontium and lead from actual ICPP sodium-bearing waste". United States. doi:10.2172/568712. https://www.osti.gov/servlets/purl/568712.
@article{osti_568712,
title = {Demonstration of a SREX flowsheet for the partitioning of strontium and lead from actual ICPP sodium-bearing waste},
author = {Law, J D and Wood, D J and Olson, L G and Todd, T A},
abstractNote = {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.},
doi = {10.2172/568712},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1997},
month = {8}
}