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Title: Development and testing of SREX flowsheets for treatment of Idaho Chemical Processing Plant sodium-bearing waste using centrifugal contactors

Abstract

Laboratory experimentation has indicated that the SREX process is effective for partitioning {sup 90}Sr from acidic radioactive waste solutions located at the Idaho Chemical Processing Plant. A baseline flowsheet has been proposed for the treatment of sodium-bearing waste (SBW) which includes extraction of strontium from liquid SBW into the SREX solvent (0.15 M 4{prime},4{prime}(5{prime})-di-(tert-butyldicyclohexo)-18-crown-6 and 1.2 M TBP in Isopar L), a 0.01 M nitric acid strip section to back-extract components from the loaded solvent, and a 2.0 M HNO{sub 3} solvent acidification section to equilibrate the solvent with HNO{sub 3} prior to recycle to the extraction section. The flowsheet was designed to provide a decontamination factor (DF) of >10{sup 3} which will reduce the {sup 90}Sr activity in the waste solution to below the NRC Class A LLW limit of 0.04 Ci {sup 90}Sr/m{sup 3}. SREX flowsheet testing was performed using sixteen stages of 5.5-cm diameter centrifugal contactors. The behavior of stable Sr and other components which are potentially extracted by the SREX solvent were evaluated. Specifically, the behavior of the matrix components including Pb, K, Hg, Na, Ca, Zr, and Fe was studied. The described flowsheet achieved 99.98% Sr removal (DF=4250) with one cycle of SREX. Potassium andmore » Zr were partially extracted into the SREX solvent with 35% and 21%, respectively, exiting in the strip product. Sodium, Ca, and Fe were essentially inextractable. Lead was determined to extract and accumulate in the SREX solvent and in the strip section. As a result, a Pb precipitate formed in the strip stages of the contactors. Mercury was also determined to extract and accumulate in the SREX solvent.« less

Authors:
; ;  [1]
  1. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
471744
Report Number(s):
CONF-951057-
Journal ID: SSTEDS; ISSN 0149-6395; TRN: 97:008848
Resource Type:
Journal Article
Journal Name:
Separation Science and Technology
Additional Journal Information:
Journal Volume: 32; Journal Issue: 1-4; Conference: 9. symposium on separation science and technology for energy applications, Gatlinburg, TN (United States), 22-26 Oct 1995; Other Information: PBD: Jan-Feb 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 40 CHEMISTRY; STRONTIUM 90; CENTRIFUGATION; SOLVENT EXTRACTION; RADIOACTIVE WASTE PROCESSING; CROWN ETHERS; INTERFERING ELEMENTS; MATHEMATICAL MODELS

Citation Formats

Law, J D, Wood, D J, and Herbst, R S. Development and testing of SREX flowsheets for treatment of Idaho Chemical Processing Plant sodium-bearing waste using centrifugal contactors. United States: N. p., 1997. Web. doi:10.1080/01496399708003196.
Law, J D, Wood, D J, & Herbst, R S. Development and testing of SREX flowsheets for treatment of Idaho Chemical Processing Plant sodium-bearing waste using centrifugal contactors. United States. doi:10.1080/01496399708003196.
Law, J D, Wood, D J, and Herbst, R S. Wed . "Development and testing of SREX flowsheets for treatment of Idaho Chemical Processing Plant sodium-bearing waste using centrifugal contactors". United States. doi:10.1080/01496399708003196.
@article{osti_471744,
title = {Development and testing of SREX flowsheets for treatment of Idaho Chemical Processing Plant sodium-bearing waste using centrifugal contactors},
author = {Law, J D and Wood, D J and Herbst, R S},
abstractNote = {Laboratory experimentation has indicated that the SREX process is effective for partitioning {sup 90}Sr from acidic radioactive waste solutions located at the Idaho Chemical Processing Plant. A baseline flowsheet has been proposed for the treatment of sodium-bearing waste (SBW) which includes extraction of strontium from liquid SBW into the SREX solvent (0.15 M 4{prime},4{prime}(5{prime})-di-(tert-butyldicyclohexo)-18-crown-6 and 1.2 M TBP in Isopar L), a 0.01 M nitric acid strip section to back-extract components from the loaded solvent, and a 2.0 M HNO{sub 3} solvent acidification section to equilibrate the solvent with HNO{sub 3} prior to recycle to the extraction section. The flowsheet was designed to provide a decontamination factor (DF) of >10{sup 3} which will reduce the {sup 90}Sr activity in the waste solution to below the NRC Class A LLW limit of 0.04 Ci {sup 90}Sr/m{sup 3}. SREX flowsheet testing was performed using sixteen stages of 5.5-cm diameter centrifugal contactors. The behavior of stable Sr and other components which are potentially extracted by the SREX solvent were evaluated. Specifically, the behavior of the matrix components including Pb, K, Hg, Na, Ca, Zr, and Fe was studied. The described flowsheet achieved 99.98% Sr removal (DF=4250) with one cycle of SREX. Potassium and Zr were partially extracted into the SREX solvent with 35% and 21%, respectively, exiting in the strip product. Sodium, Ca, and Fe were essentially inextractable. Lead was determined to extract and accumulate in the SREX solvent and in the strip section. As a result, a Pb precipitate formed in the strip stages of the contactors. Mercury was also determined to extract and accumulate in the SREX solvent.},
doi = {10.1080/01496399708003196},
journal = {Separation Science and Technology},
number = 1-4,
volume = 32,
place = {United States},
year = {1997},
month = {1}
}