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Demonstration of Caustic-Side Solvent Extraction with Optimized Solvent int he 2-CM Centrifugal Contactor Apparatus Using Dissolved Salt Cake from Tank 37H.

DE2004806926

Publication Date	2002
Personal Author	Norato, M. A.; Fink, S. D.; Fondeur, F. F.; Kessinger, G. F.; Pierce, R. A.; Walker, D. D.
Page Count	50
Abstract	Researchers successfully demonstrated the chemistry of the Caustic-Side Solvent Extraction (CSSX) flow sheet with optimized solvent. This represents the third such process demonstration using actual Savannah River Site (SRS) high level waste (HLW). The present test differed from previous studies in the use of radioactive waste derived from Tank 37H dissolved salt cake, as opposed to supernate solutions used in previous demonstrations.
Keywords	Solvent extraction Cesium High-level radioactive wastes Flowsheets Separation processes Solvents Testing Solubility Radioactive wastes Savannah River Plant CSSX process Salt cakes CSSX(Caustic-side solvent extraction)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Westinghouse Savannah River Co., Aiken, SC. Savannah River Site.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200424

Demonstration of Caustic-Side Solvent Extraction with Optimized Solvent int he 2-CM Centrifugal Contactor Apparatus Using Dissolved Salt Cake from Tank 37H.

Demonstration of Caustic-Side Solvent Extraction with Optimized Solvent int he 2-CM Centrifugal Contactor Apparatus Using Dissolved Salt Cake from Tank 37H.
DE2004806926

Publication Date	2002
Personal Author	Norato, M. A.; Fink, S. D.; Fondeur, F. F.; Kessinger, G. F.; Pierce, R. A.; Walker, D. D.
Page Count	50
Abstract	Researchers successfully demonstrated the chemistry of the Caustic-Side Solvent Extraction (CSSX) flow sheet with optimized solvent. This represents the third such process demonstration using actual Savannah River Site (SRS) high level waste (HLW). The present test differed from previous studies in the use of radioactive waste derived from Tank 37H dissolved salt cake, as opposed to supernate solutions used in previous demonstrations.
Keywords	Solvent extraction Cesium High-level radioactive wastes Flowsheets Separation processes Solvents Testing Solubility Radioactive wastes Savannah River Plant CSSX process Salt cakes CSSX(Caustic-side solvent extraction)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Westinghouse Savannah River Co., Aiken, SC. Savannah River Site.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200424