Development of a cobalt dicarbollide/polyethylene glycol solvent extraction process for separation of cesium and strontium to support advanced aqueous reprocessing

A chlorinated cobalt dicarbollide(CCD)/polyethylene glycol (PEG) based solvent extraction process is being developed for the separation of Cs and Sr from leached spent light water reactor (LWR) fuel as part of the Advanced Fuel Cycle Initiative (AFCI). The separation of Cs and Sr would significantly...

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Bibliographic Details
Published in:Nuclear technology 2004-08, Vol.147 (2), p.284-290
Main Authors: LAW, Jack D, HERBST, R. Scott, PETERMAN, Dean R, TILLOTSON, Rich D, TODD, Terry A
Format: Article
Language:English
Subjects:
AMERICIUM 241
Applied sciences
CESIUM
CESIUM 137
CHARGE-COUPLED DEVICES
COBALT
Energy
Energy. Thermal use of fuels
EUROPIUM 154
Exact sciences and technology
Fission nuclear power plants
FUEL CYCLE
Fuels
Installations for energy generation and conversion: thermal and electrical energy
NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Nuclear fuels
POLYETHYLENE GLYCOLS
Preparation and processing of nuclear fuels
SOLVENT EXTRACTION
SOLVENTS
SPENT FUELS
STRONTIUM
STRONTIUM 85
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
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Summary:A chlorinated cobalt dicarbollide(CCD)/polyethylene glycol (PEG) based solvent extraction process is being developed for the separation of Cs and Sr from leached spent light water reactor (LWR) fuel as part of the Advanced Fuel Cycle Initiative (AFCI). The separation of Cs and Sr would significantly reduce the heat generation of spent nuclear fuel requiring geologic disposal. A solvent composition for this process has been verified, and the distribution coefficient acid dependency for Cs, Sr, Am, and Eu have been measured for the CCD/PEG solvent. Leached spent fuel simulant, traced with {sup 137}Cs, {sup 85}Sr, {sup 241}Am, and {sup 154}Eu, was used to perform batch contact flowsheet experiments for the extraction, scrub, and strip sections of the CCD/PEG process. Additionally, the effects of acetohydroxamic acid and its decomposition products, as well as the effects of the uranium extraction (UREX) process solvent, on the extraction of Cs and Sr with the CCD/PEG process were evaluated.
ISSN:0029-5450
1943-7471
DOI:10.13182/NT04-5