Optimization Studies for the Recovery of Thorium from Advanced Heavy Water Reactor High Level Waste (AHWR-HLW) Solutions Using Green Solvents
- 1 January 2013
- journal article
- extraction
- Published by Taylor & Francis Ltd in Separation Science and Technology
- Vol. 48 (4), 626-633
- https://doi.org/10.1080/01496395.2012.707733
Abstract
An Advanced Heavy Water Reactor (AHWR) has been specifically designed to exploit Th/233U as fuels. The reprocessing is focused mainly on the recovery of 233U and Pu from the spent fuels leaving bulk of Th (∼100 g/L) in the High Level Waste (HLW) solutions. No systematic attempts have been made so far to identify suitable solvents for the recovery of thorium from high level waste (HLW) solutions generated after AHWR spent fuel reprocessing. Tri-n-butyl phosphate (TBP), though the work horse for nuclear fuel reprocessing as an extractant, suffers from the serious limitation of third-phase formation during the extraction of macro concentrations of thorium. Two straight chain dialkyl amides such as N,N-dihexyl octanamide (DHOA), and N,N-dihexyl decanamide (DHDA) as well as TBP were evaluated for the recovery of the thorium from AHWR-HLW solutions. Attempts were made to identify suitable solvent (extractant + diluent) system and optimize the conditions for the recovery of thorium from HLW solutions. Selectivity of the solvents was examined for thorium extraction over fission products/structural materials under AHWR raffinate solutions. Counter-current centrifugal contactor runs were also carried out on simulated waste solutions to validate the optimized conditions for the recovery of thorium from the simulated AHWR waste solutions.Keywords
This publication has 22 references indexed in Scilit:
- Validation of the flow-sheet proposed for reprocessing of AHWR spent fuel: counter-current studies using TBPDesalination and Water Treatment, 2012
- Studies on the Development of a Flow-Sheet for AHWR Spent Fuel Reprocessing Using TBPSeparation Science and Technology, 2010
- Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactorNuclear Engineering and Design, 2006
- Distribution Behavior of U(VI), Th(IV), and Fission Products with Di(2-ethylhexyl) Isobutyramide under Process ConditionsIndustrial & Engineering Chemistry Research, 2004
- Amides and diamides as promising extractants in the back end of the nuclear fuel cycle: an overviewSeparation and Purification Technology, 2004
- EVALUATION OF DI(2-ETHYLHEXYL)ISOBUTYRAMIDE (D2EHIBA) AS A PROCESS EXTRACTANT FOR THE RECOVERY OF233U FROM IRRADIATED ThSolvent Extraction and Ion Exchange, 2002
- Completely Incinerable Extractants for the Nuclear Industry - A ReviewMineral Processing and Extractive Metallurgy Review, 1997
- SYNTHESIS AND USES OF THE AMIDES EXTRACTANTSSolvent Extraction and Ion Exchange, 1989
- Potentiality of Nonorganophosphorus Extractant in Chemical Separations of ActinidesSeparation Science and Technology, 1988
- APPLICATION OF AMIDES AS EXTRACTANTSPublished by Office of Scientific and Technical Information (OSTI) ,1961