Tri-n-butyl phosphate as an extracting solvent for inorganic nitrates—V

Alcock, K.; Best, G.F.; Hesford, E.; McKay, H.A.C.

doi:10.1016/0022-1902(58)80116-5

Cited by 85 publications

(24 citation statements)

References 7 publications

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“…In the present study, we introduced solutions of 3 M HNO 3 containing Pu(IV) and TBP diluted with n-dodecane into a glass chip microchannel. Plutonium concentration of the solution at the outlet of the microchip was measured to analyze the extraction reaction behavior of Pu(IV) with TBP in the microchannel.…”

Section: Discussionmentioning

confidence: 99%

“…A solution of TBP in n-dodecane was prepared by diluting 30 mL of TBP in 100 mL of n-dodecane (30% TBP/n-dodecane). Metallic Pu (NBL CRM126, New Brunswick Laboratory, USA) was dissolved in 3 M HNO 3 and purified with TEVA resin (Eichrom Technologies) to eliminate small quantities of Am generated from 241 Pu decay. Then, the oxidation state of Pu was adjusted to +4 by adding 100 L of H 2 O 2 .…”

Section: Reagentsmentioning

confidence: 99%

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Evaluation of plutonium(IV) extraction rate between nitric acid and tri‐n‐butylphosphate solution using a glass chip microchannel

Yamamoto

Taguchi

Sato

et al. 2015

J of Separation Science

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Extraction of Pu(IV) with tri-n-butylphosphate is performed using a glass chip microchannel to evaluate the extraction rate. Two-phase flow forms in the microchannel by introducing a solution of Pu(IV) and tri-n-butylphosphate with flow rates above 5 μL/min. The Pu(IV) extraction reaction proceeds at the interface between the two phases. To evaluate the extraction rate, the contact time between the two phases is varied from 0.48 to 4.8 s by changing the confluent length of the microchannel and the flow rate. The Pu concentration of each phase collected from the microchannel is measured with an alpha liquid scintillation counter, and the contact time dependence of Pu(IV) extraction is obtained. An extraction model based on diffusion in the microchannel and the reaction at the interface is proposed and applied to determine the extraction rate. The extraction process is assumed to follow pseudo-first-order kinetics, and the extraction rate constant of Pu(IV) is determined to be 1.5 × 10(-2) cm/s. The investigation demonstrates that a microfluidic device can be a new tool to determine Pu(IV) extraction rates.

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Section: Discussionmentioning

confidence: 99%

Section: Reagentsmentioning

confidence: 99%

Evaluation of plutonium(IV) extraction rate between nitric acid and tri‐n‐butylphosphate solution using a glass chip microchannel

Yamamoto

Taguchi

Sato

et al. 2015

J of Separation Science

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“…Some of the more noted publications include Tsvetkova et al (1961), Adamskii et al (1980), Alcock et al (1957), Egorov et al (1960), Benedict et al (1981), Nikitina and Pushlenkov (1962), and Reznik et al (1963). They all give Eq.…”

Section: Objectives and Relevancementioning

confidence: 95%

Zirconium transport dynamics in the Purex solvent extraction process

DeMuth

Counce

1992

AIChE Journal

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The primary objective of this study was to develop and validate experimental and mathematical procedures that can be used to determine the fundamental mechanisms of the Purex (plutonium and uranium) extraction process. The mechanisms of this solvent extraction process have been established by classical chemical engineering principles. In the past, modeling of transport phenomena for the solvent extraction of spent nuclear fuel by the Purex process has typically (1) relied solely on diffusion, (2) relied solely on chemical reaction, (3) combined diffusion and chemical reaction in a semiempirical fashion, or (4) combined diffusion and chemical reaction in a nonclassical chemical engineering manner. This study was conducted with the single Purex species, aqueous Zr4+, to simplify the chemistry and modeling mathematics. The validated procedures and model are applicable to most all Purex species.

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“…The system can be used to extract and separate Y and the lower lanthanides (La-Gd) also. In extraction of trace level quanti ties out of nitric acid solutions into TBP the ease of extraction increased in the order Pu (IV) > N p (IV) > Th, but reversed for the metals in the higher oxidation state, i.e., U (VI) > Np(VI) > Pu (VI) (64) . Sato (65) has determined distribution ratio data for uranyl nitrate into TBP (65) .…”

Section: Ion Association Systemsmentioning

confidence: 97%

Solvent Extraction in Radiochemical Separations

Freiser¹,

Morrison²

1959

Annu. Rev. Nucl. Sci.

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The last several years have seen a reawakening appreciation of the value of solvent extraction separations processes both on analytical and process scales. Separations by solvent extraction are simple, convenient, clean, and applicable equally well to carrier-free tracer and macro amounts of materials. They usually require apparatus as uncomplicated as a separatory funnel and may readily be adapted to remote handling procedures.A variety of separations techniques have been applied to the problems of isolation and radiochemical purification of nuclides. General descriptions and recent surveys of radiochemical separations can be found in references (1) through (5). Although all of the separation methods mentioned are of great importance to the radiochemist, solvent extraction is particularly well suited to the purification of many radioisotopes since, after several extractions of a substance, the final product is usually relatively free from extraneous im purities which may be present when other separation procedures are em ployed. Also, if the isotope of interest has a short half life, a rapid separation is essential and extraction procedures have proved invaluable. Most of the extractions employed in radiochemistry are based on previously developed conventional analytical extractions, and the recent book by the authors (6) offers a comprehensive treatment of the subject of extraction as applied to inorganic analysis. In addition to covering the principles and practical as pects of the technique, procedures for the extraction of the elements are presented. The review by the authors (7) in Analytical Chemistry surveys the latest developments in the field. CLASSIFICATION OF SOLVENT EXTRACTION SYSTEMSMost metal salts are strong electrolytes that are relatively insoluble in organic solvents and soluble in water because of its ability to solvate the ions as well as because of its high dielectric constant. Since it is usually necessary to transform the hydrated metal ion into an uncharged complex in order to extract it into an organic solvent, it is convenient to classify metal extraction systems on the basis of the nature of the extractable metal 1 The survey of literature pertaining to this review was completed in December, 1958.2 Among the abbreviations used in this chapter are: EDTA (ethylenediamine tetraacetic acid); HDGP (dioctylphenyl orthophosphoric acid); TBP (tributyl phos phate); TTA (thenoyltrifluoracetone).

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Tri-n-butyl phosphate as an extracting solvent for inorganic nitrates—V

Cited by 85 publications

References 7 publications

Evaluation of plutonium(IV) extraction rate between nitric acid and tri‐n‐butylphosphate solution using a glass chip microchannel

Evaluation of plutonium(IV) extraction rate between nitric acid and tri‐n‐butylphosphate solution using a glass chip microchannel

Zirconium transport dynamics in the Purex solvent extraction process

Solvent Extraction in Radiochemical Separations

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