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

Citation
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
Citations number
16
Categorie Soggetti
Chemistry
Journal title
SOLVENT EXTRACTION AND ION EXCHANGE
ISSN journal
07366299 → ACNP
Volume
19
Issue
1
Year of publication
2001
Pages
23 - 36
Database
ISI
SICI code
0736-6299(2001)19:1<23:TUSE(P>2.0.ZU;2-G
Abstract
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.