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JournalISSN: 0736-6299

Solvent Extraction and Ion Exchange 

Taylor & Francis
About: Solvent Extraction and Ion Exchange is an academic journal published by Taylor & Francis. The journal publishes majorly in the area(s): Extraction (chemistry) & Aqueous solution. It has an ISSN identifier of 0736-6299. Over the lifetime, 2094 publications have been published receiving 48024 citations. The journal is also known as: Solvent extraction & ion exchange.


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Journal ArticleDOI
TL;DR: In this paper, the effect of nitric acid concentration on the selectivity of a novel extraction chromatographic resin consisting of an octanol solution of 4,4′(5′)-bis(t-butyl-cyclohexano)-18-crown-6 sorbed on an inert polymeric support for strontium over a number of alkali, alkaline earth, and other metal cations was evaluated.
Abstract: The effect of nitric acid concentration on the selectivity of a novel extraction chromatographic resin consisting of an octanol solution of 4,4′(5′)-bis(t-butyl-cyclohexano)-18-crown-6 sorbed on an inert polymeric support for strontium over a number of alkali, alkaline earth, and other metal cations was evaluated. The effect of macro quantities of selected elements on strontium retention by the resin was also examined. The resin is shown to exhibit excellent selectivity for strontium over nearly all of the test elements; only lead and tetravalent neptunium, polonium, and plutonium show significant affinity for the material. In addition, concentrations of calcium or sodium ion up to ∼ 0.1 M. are shown not to diminish the sorption of strontium appreciably. Several useful radiochemical separation schemes devised on the basis of the results obtained are described.

686 citations

Journal ArticleDOI
TL;DR: In this paper, six diglycolamide molecules were used for actinide extraction from nitric acid into n-dodecane, and the dependence of the distribution coefficients of Eu(III) and Am(III), on the length of alkyl chain in the extractants was examined.
Abstract: The novel extractants, six diglycolamides synthesized in our laboratory, were investigated for actinide extraction from nitric acid into n-dodecane. The dependence of the distribution coefficients of Eu(III) and Am(III) on the length of alkyl chain in the extractants was examined. Among the diglycolamides studied, N,N,N′,N′-tetraoctyl-3-oxapentanediamide (TOOPDA) and N,N,N′,N′-tetradecyl-3-oxapentanediamide (TDOPDA) showed a sufficient solubility in n-dodecane, due to their appropriate lipophilicity modified by increasing the length of the alkyl chain attached to amidic N atoms. The distribution coefficients, D M, of actinides obtained by TOOPDA increased with an increase in HNO3 concentration. The number of diglycolamide molecules coordinated to the actinide ions was estimated to be three for Th(IV), U(VI), Pu(IV), and four for Am(III) and Cm(III) by slope analysis. The order of D M for the actinides at high nitric acid concentrations is An(III), An(IV) > An(VI) > An(V) and that for lanthanides, heavier ...

620 citations

Journal ArticleDOI
TL;DR: A review of the results of the past 10-12 years on the separation of trivalent lanthanides and actinides, both intra-, and intergroup, can be found in this article.
Abstract: Among the most difficult of separations of metal ions are the intra- and intergroup separation of Ianthanides and trivalent actinides. Yet environmental concerns related to radioactivity, and new high-tech developments which have increased the demand for pure lanthanides have combined to foster a greater need for effective procedures to attain these separations. The most recent review which concentrated on this problem is now nearly 20 years old. While the methods developed over the preceeding 50-60 years of research are still in use, new understanding and some promising new methods are currently under development. The present manuscript is partly a tutorial of the basic chemical principles leading to successful separations, and partly a review of the results of the past 10-12 years on the separation of trivalent lanthanides and actinides, both intra-, and intergroup.

469 citations

Journal ArticleDOI
TL;DR: In this paper, a review of the state-of-the-art reagents and methods for hydrometallurgical partitioning of actinides from different types of transuranium wastes and dissolved fuels is presented.
Abstract: Reagents and methods that have been developed during the past 20 years for hydrometallurgical partitioning of actinides from different types of transuranium (TRU) wastes and dissolved fuels are reviewed. Emphasis is placed on the extraction performance of the fully-optimized reagents rather than on the structural iterations that were undertaken (and in some cases are still being conducted) to identify the optimum species. Particular attention is paid to separation processes that have been demonstrated in batch and counter-current solvent extraction, and batch and column mode extraction chromatography. The salient features of the various techniques and reagents for actinide recycle are compared. Sections of the review focus on neptunium behavior in hydrometallurgy and on characterization of those reagents best suited to the separation of trivalent actinides from fission product lanthanides. Selected flowsheets that have been reported for the separation and recovery of actinides from TRU wastes are presented.

457 citations

Journal ArticleDOI
TL;DR: A generic transurantc (TRU) element extraction/recovery process was developed based on the use of octyl(phenyl)-N,N-diiso-butylcarbamoylmetliylphosphine oxide, 0φD(iB)CMPO, dissolved in PUREX process solvent (tribntyl phosphate, TBP, in normal paraffluic hydrocarbon, NPH) as mentioned in this paper.
Abstract: A generic transurantc (TRU) element extraction/recovery process was developed based on the use of octyl(phenyl)-N,N-diiso-butylcarbamoylmetliylphosphine oxide, 0φD(iB)CMPO, dissolved in PUREX process solvent (tribntyl phosphate, TBP, in normal paraffluic hydrocarbon, NPH). The process (called TRUEX) is capable of reducing the TRU concentration by many orders of magnitude In waste solutions containing a wide range of nitric acid, salt, and fission product concentrations. A major feature of the process is that it is readily adaptable for waste processing in existing fuel reprocessing facilities.

444 citations

Performance
Metrics
No. of papers from the Journal in previous years
YearPapers
202328
202216
202164
202046
201937
201845