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Title: Development of a Cobalt Dicarbollide/Polyethylene Glycol Solvent Extraction Process for Separation of Cesium and Strontium to Support Advanced Aqueous Reprocessing

Journal Article · · Nuclear Technology
OSTI ID:20840214
; ; ; ;  [1]
  1. Idaho National Engineering and Environmental Laboratory (United States)

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.

OSTI ID:
20840214
Journal Information:
Nuclear Technology, Vol. 147, Issue 2; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 0029-5450
Country of Publication:
United States
Language:
English