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Title: Solvent extraction of radionuclides from aqueous tank waste

Abstract

This task aims toward the development of efficient solvent-extraction processes for the removal of the fission products {sup 99}Tc, {sup 90}Sr, and {sup 137}Cs from alkaline tank wastes. Processes already developed or proposed entail direct treatment of the waste solution with the solvent and subsequent stripping of the extracted contaminants from the solvent into a dilute aqueous solution. Working processes to remove Tc(and SR) separately and Cs separately have been developed; the feasibility of a combined process is under investigation. Since Tc, Sr, and Cs will be vitrified together in the high-level fraction, however, a process that could separate Tc, Sr, and Cs simultaneously, as opposed to sequentially, potentially offers the greatest impact. A figure presents a simplified diagram of a proposed solvent-extraction cycle followed by three possible treatments for the stripping solution. Some degree of recycle of the stripping solution (option a) is expected. Simple evaporation (option c) is possible prior to vitrification; this offers the greatest possible volume reduction with simple operation and no consumption of chemicals, but it is energy intensive. However, if the contaminants are concentrated (option b) by fixed-bed technology, the energy penalty of evaporation can be avoided and vitrification facilitated without any additional secondarymore » waste being produced.« less

Authors:
; ;  [1];  [2];  [3]
  1. Oak Ridge National Lab., TN (United States). Chemical and Analytical Sciences Div.
  2. Argonne National Lab., IL (United States). Chemical Technology Div.
  3. Pacific Northwest National Lab., Richland, WA (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
OSTI Identifier:
425255
Report Number(s):
CONF-970148-1
ON: DE97001645; TRN: 97:003065
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Conference
Resource Relation:
Conference: Efficient Separations and Processing (ESP) Crosscutting Program FY 1997 technical exchange meeting, Gaithersburg, MD (United States), 28-30 Jan 1997; Other Information: PBD: [1997]
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; RADIOACTIVE WASTE PROCESSING; SOLVENT EXTRACTION; TECHNETIUM 99; STRONTIUM 90; CESIUM 137; LIQUID WASTES; ADSORBENTS; CROWN ETHERS

Citation Formats

Moyer, B A, Bonnesen, P V, Sachleben, R A, Leonard, R A, and Lumetta, G J. Solvent extraction of radionuclides from aqueous tank waste. United States: N. p., 1997. Web.
Moyer, B A, Bonnesen, P V, Sachleben, R A, Leonard, R A, & Lumetta, G J. Solvent extraction of radionuclides from aqueous tank waste. United States.
Moyer, B A, Bonnesen, P V, Sachleben, R A, Leonard, R A, and Lumetta, G J. 1997. "Solvent extraction of radionuclides from aqueous tank waste". United States. https://www.osti.gov/servlets/purl/425255.
@article{osti_425255,
title = {Solvent extraction of radionuclides from aqueous tank waste},
author = {Moyer, B A and Bonnesen, P V and Sachleben, R A and Leonard, R A and Lumetta, G J},
abstractNote = {This task aims toward the development of efficient solvent-extraction processes for the removal of the fission products {sup 99}Tc, {sup 90}Sr, and {sup 137}Cs from alkaline tank wastes. Processes already developed or proposed entail direct treatment of the waste solution with the solvent and subsequent stripping of the extracted contaminants from the solvent into a dilute aqueous solution. Working processes to remove Tc(and SR) separately and Cs separately have been developed; the feasibility of a combined process is under investigation. Since Tc, Sr, and Cs will be vitrified together in the high-level fraction, however, a process that could separate Tc, Sr, and Cs simultaneously, as opposed to sequentially, potentially offers the greatest impact. A figure presents a simplified diagram of a proposed solvent-extraction cycle followed by three possible treatments for the stripping solution. Some degree of recycle of the stripping solution (option a) is expected. Simple evaporation (option c) is possible prior to vitrification; this offers the greatest possible volume reduction with simple operation and no consumption of chemicals, but it is energy intensive. However, if the contaminants are concentrated (option b) by fixed-bed technology, the energy penalty of evaporation can be avoided and vitrification facilitated without any additional secondary waste being produced.},
doi = {},
url = {https://www.osti.gov/biblio/425255}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1997},
month = {Wed Jan 01 00:00:00 EST 1997}
}

Conference:
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