Please use this identifier to cite or link to this item:
|Title:||Modelling of tritium distribution coefficients in 30 Vol% TBP/n-dodecane/UO2(NO3) 2/ nitric acid system|
|Abstract:||Stringent environmental norms require confinement of tritium and its proper disposal during solvent extraction operations of reprocessing. Current solvent extraction flowsheets, for reprocessing the spent nuclear fuel, have provision for tritium scrubbing from loaded solvent. Quantitative models for tritium distribution are not available in the literature. In this communication, an empirical model is reported for correlating the tritium distribution coefficient in nitric acid-30% TBP/n-dodecane system to aqueous nitric acid and free TBP.|
|ISSN:||0975-0991 (Online); 0971-457X (Print)|
|Appears in Collections:||IJCT Vol.08(1) [January 2001]|
Items in NOPR are protected by copyright, with all rights reserved, unless otherwise indicated.