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Title: Demonstration of the SREX process for the removal of {sup 90}Sr from actual highly radioactive solutions in centrifugal contactors

Abstract

The SREX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of {sup 90}Sr from acidic radioactive wastes stored at the ICPP. These efforts have culminated in a recent demonstration of the SREX process with actual tank waste. This demonstration was performed using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded hot cell at the ICPP Remote Analytical Laboratory. An overall removal efficiency of 99.995% was obtained for {sup 90}Sr. As a result, the activity of {sup 90}Sr was reduced from 201 Ci/m{sup 3} in the feed solution of 0.0089 Ci/m{sup 3} in the aqueous raffinate, which is below the U.S. NRC Class A LLW limit of 0.04 Ci/m{sup 3} for {sup 90}Sr. Lead was extracted by the SREX solvent and successfully partitioned from the {sup 90}Sr using an ammonium citrate strip solution. Additionally, 94% of the total alpha activity, 1.9% of the {sup 241}Am, 99.94% of the {sup 238}Pu, 99.97% of the {sup 239}Pu, 36.4% of the K, 64% of the Ba, and >83% of the Zr were extracted by the SREX solvent. Cs, B, Cd, Ca, Cr, Fe, Mn, Ni, and Na were essentially inextractable. 10 refs., 2 figs., 3more » tabs.« 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:
565286
Report Number(s):
INEL/CON-97-00706; CONF-971004-
ON: DE98050470; TRN: 98:002530
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Conference
Resource Relation:
Conference: GLOBAL `97: international conference on future nuclear systems, Yokohama (Japan), 5-10 Oct 1997; Other Information: PBD: 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; HIGH-LEVEL RADIOACTIVE WASTES; TANKS; STRONTIUM 90; SOLVENT EXTRACTION; EFFICIENCY; LEAD; AMERICIUM 241

Citation Formats

Law, J D, Wood, D J, Todd, T A, and Olson, L G. Demonstration of the SREX process for the removal of {sup 90}Sr from actual highly radioactive solutions in centrifugal contactors. United States: N. p., 1997. Web.
Law, J D, Wood, D J, Todd, T A, & Olson, L G. Demonstration of the SREX process for the removal of {sup 90}Sr from actual highly radioactive solutions in centrifugal contactors. United States.
Law, J D, Wood, D J, Todd, T A, and Olson, L G. Wed . "Demonstration of the SREX process for the removal of {sup 90}Sr from actual highly radioactive solutions in centrifugal contactors". United States. https://www.osti.gov/servlets/purl/565286.
@article{osti_565286,
title = {Demonstration of the SREX process for the removal of {sup 90}Sr from actual highly radioactive solutions in centrifugal contactors},
author = {Law, J D and Wood, D J and Todd, T A and Olson, L G},
abstractNote = {The SREX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of {sup 90}Sr from acidic radioactive wastes stored at the ICPP. These efforts have culminated in a recent demonstration of the SREX process with actual tank waste. This demonstration was performed using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded hot cell at the ICPP Remote Analytical Laboratory. An overall removal efficiency of 99.995% was obtained for {sup 90}Sr. As a result, the activity of {sup 90}Sr was reduced from 201 Ci/m{sup 3} in the feed solution of 0.0089 Ci/m{sup 3} in the aqueous raffinate, which is below the U.S. NRC Class A LLW limit of 0.04 Ci/m{sup 3} for {sup 90}Sr. Lead was extracted by the SREX solvent and successfully partitioned from the {sup 90}Sr using an ammonium citrate strip solution. Additionally, 94% of the total alpha activity, 1.9% of the {sup 241}Am, 99.94% of the {sup 238}Pu, 99.97% of the {sup 239}Pu, 36.4% of the K, 64% of the Ba, and >83% of the Zr were extracted by the SREX solvent. Cs, B, Cd, Ca, Cr, Fe, Mn, Ni, and Na were essentially inextractable. 10 refs., 2 figs., 3 tabs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1997},
month = {10}
}

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