The universal solvent extraction (UNEX) process. II. Flowsheet developmentand demonstration of the UNEX process for the separation of cesium, strontium, and actinides from actual acidic radioactive waste
Jd. Law et al., The universal solvent extraction (UNEX) process. II. Flowsheet developmentand demonstration of the UNEX process for the separation of cesium, strontium, and actinides from actual acidic radioactive waste, SOLVENT EXT, 19(1), 2001, pp. 23-36
A novel solvent extraction process, the Universal Extraction (UNEX) process
, has been developed for the simultaneous separation of cesium, strontium,
and the actinides from acidic waste solutions. The UNEX process solvent con
sists: of chlorinated cobalt dicarbollide for the extraction of Cs-137, pol
yethylene glycol for the extraction of Sr-90, and diphenyl-N,N-dibutylcarba
moyl phosphine oxide for the extraction of the actinides and lanthanides. A
nonnitroaromatic polar diluent consisting of phenyltrifluoromethyl sulfone
has been developed for this process. A UNEX flowsheet consisting of a sing
le solvent extraction cycle has been developed as a part of a collaborative
effort between the Khlopin Radium Institute (KRI) and the Idaho National E
ngineering and Environmental Laboratory (INEEL). This flowsheet has been de
monstrated with actual acidic radioactive tank waste at the INEEL using 24
stages of 2-cm diameter centrifugal contactors installed in a shielded cell
facility. The activities of Cs-137, Sr-90, and the actinides were reduced
to levels at which a grout waste form would meet NRC Class A LLW requiremen
ts. The extraction of Tc-99 and several nonradioactive metals by the UNEX s
olvent has also been evaluated.