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Journal ArticleDOI

EXTRACTION OF Am FROM NITRIC ACID BY CARBAMOYL-PHOSPHORYL EXTRACTANTS: THE INFLUENCE OF SUBSTITUENTS ON THE SELECTIVITY OF Am OVER Fe AND SELECTED FISSION PRODUCTS

TLDR
A number of neutral extractants containing the P(0)(CH2)nC(0)N raolety were evaluated for their ability to extract Am from nitric acid and their selectivity for Am over Fe and selected fission products as discussed by the authors.
Abstract
A number of neutral extractants containing the P(0)(CH2)nC(0)N raolety were evaluated for their ability to extract Am from nitric acid and their selectivity for Am over Fe and selected fission products. Extractants containing alkoxy, alkyl, and aryl substltuents were evaluated. Tetrachloroethylene was used as a diluent. Fission products selected for study were Y, Zr, Mo, Tc, Ru, Rh, Pd, La, Ce, Pr, Nd, Sra, and Eu. The conclusions drawn were that the most efficient and selective Am extractant contains a single carbon bridging group, one or two phenyl groups attached to the phosphorus atom and l9obutyl groups attached to the amide nitrogen.

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Journal ArticleDOI

Separation and preconcentration of uranium from acidic media by extraction chromatography

TL;DR: In this paper, the effect of macro levels of selected elements on the sorption of actinide ions by a novel extraction chromatographic resin comprised of a solution of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide in tri-n-butyl phosphate supported on an inert polymeric substrate is described.
Journal ArticleDOI

Actinide partitioning—a review

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.
Journal ArticleDOI

N,N,N′,N′‐Tetraoctyl Diglycolamide (TODGA): A Promising Extractant for Actinide‐Partitioning from High‐Level Waste (HLW)

TL;DR: In this article, the authors evaluated TODGA as an extractant for the partitioning of minor actinides from simulated high level nuclear waste solutions and found that TODGA molecules display a tendency toward aggregation in n−dodecane at lower acidities.
Journal ArticleDOI

The Truex Process and the Management of Liquid Tru Uwaste

TL;DR: The TRUEX (TRansUranium Extraction) process is a new generic actinide extraction/recovery process for the removal of all actinides from acidic nitrate and chloride nuclear waste solutions as discussed by the authors.
Journal ArticleDOI

Ligands for f-element extraction used in the nuclear fuel cycle

TL;DR: It appears that small modifications of the structure of the ligand, the pre-organising platform or the solvent can have significant impact on the extraction (and separation) of metal ions.
References
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Book

Metal Ions in Solution

John Burgess
Journal ArticleDOI

THE TRUEX PROCESS - A PROCESS FOR THE EXTRACTION OF THE TKANSURANIC ELEMENTS EROM NITRIC AC In WASTES UTILIZING MODIFIED PUREX SOLVENT*

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.
Journal ArticleDOI

Selected Alkyl(phenyl)-N,N-dialkylcarbamoylmethylphosphine Oxides as Extractants for Am(III) from Nitric Acid Media

TL;DR: In this paper, neutral bifunctional extractants, alkyl(phenyl)-N,N-dialkyl carbamoylmethylphosphine oxides, have been prepared and studied as extractants for Am(III) from nitric acid media.
Journal ArticleDOI

THE EXTRACTION OF Am(III) FROM NITRIC ACID BY OCTYL(PHENYL)-N,N-DIISOBUTYLCARBAMOYLMETHYLPHOSPHINE OXIDE - TRI-n-BUTYL PHOSPHATE MIXTURES

TL;DR: In this article, TBP was used as a phase modifier to improve the performance of Am(III) from nitric acid using OOD[IB]CMPO and tributylphosphate.
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