Third Phase Formation in the Extraction of Plutonium by Tri-n-Butyl Phosphate

Srinivasan, T. G.; Ahmed, M.K.; Shakila, A; Dhamodaran, R.; Rao, P. R. Vasudeva; Mathews, C.K.

doi:10.1524/ract.1986.40.3.151

Cited by 62 publications

(9 citation statements)

References 5 publications

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“…Third phase formation with Pu(IV) is considered to be an important drawback when it comes to the reprocessing of fast reactor fuels, since the content of Pu in spent FBR fuel is much higher than that in spent LWR fuel. The third phase formation tendency of Pu(IV) by TBP increases in the presence of U(VI) [18]. In India, the spent fuel discharged from FBTR is being reprocessed in compact reprocessing of advanced fuels in Lead minicells (CORAL).…”

Section: Introductionmentioning

confidence: 99%

Solvent extraction studies with some fission product elements from nitric acid media employing tri-iso-amyl phosphate and tri-n-butyl phosphate as extractants

Sreenivasulu

Suresh

Sivaraman

et al. 2014

J Radioanal Nucl Chem

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Tri-iso-amyl phosphate (TiAP) has been identified as an alternate extractant to tri-n-butyl phosphate (TBP) for the reprocessing of fast reactor fuels. In the present work, extraction behaviour of some fission product elements such as Zr(IV), RuNO(III), TcO À 4 , La(III), Ce(III) and Nd(III) along with Am(III) has been investigated with 1.1 M solutions of TiAP and TBP in n-alkane diluents from nitric acid medium. The extraction of Zr(IV) has been evaluated with unirradiated and gamma irradiated solvents as a function of organic phase uranium(VI) loading. The influence of degradation products of TiAP and TBP on the extraction behaviour of fission products has also been examined. The effect of diluent degradation products and effect of alkali wash on the extraction of Zr(IV) is discussed. The formation of interfacial deposits during the washing of gamma irradiated solvents with alkali solution is also discussed.

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Section: Introductionmentioning

confidence: 99%

Solvent extraction studies with some fission product elements from nitric acid media employing tri-iso-amyl phosphate and tri-n-butyl phosphate as extractants

Sreenivasulu

Suresh

Sivaraman

et al. 2014

J Radioanal Nucl Chem

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“…In our laboratory, a systematic study of the extraction of actinide ions by trialkyl phosphates has been initiated and detailed studies have been carried out on third phase formation in plutonium and thorium systems and U(VI)/Th(IV) Separation [9][10][11][12]. We have also reported earlier the results of a study on the effect of temperature on the extraction of uranium(VI) by TAP [13].…”

Section: Introductionmentioning

confidence: 99%

Effect of Temperature on the Extraction of Plutonium(VI) by Tri n-Amyl Phosphate

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Plutonium(VI) / Solvent extraction / Enthalpy of extraction / Tri n-amyl phosphate SummaryThe effect of temperature on the extraction of plutoniuni(VI) by tri n-amyl phosphate (TAP) from nitric acid media has been studied and the results are reported here. The enthalpies for the extraction derived from the distribution ratios are found to be exothermic, like the enthalpies of extraction of Pu(VI) by tri nbutyl phosphate (TBP). Attempts have been raade to evaluate the free energy change, the entropy change and the equilibrium constant, for the extraction reaction of this ion from the enthalpy of extraction. Results of studies on the extraction of nitric acid by TAP are also reported.

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“…Based on these results, it is clear that Pu(IV) will induce the formation of the third phase as does Th(IV). Additionally, the maximum total load in metallic cations for a 1 M TBP phase is estimated at about 0.5 M. It has also been shown that the behavior of third phase formation with Pu(IV) is not linear according to aqueous HNO 3 concentration, and much more sensitive to temperature than Th(IV) [ 11 , 28 ]. Thus, although process optimization will be needed, the temperature induced phase splitting is expecting to perform better in the presence of Pu(IV) than in the presence of Th(IV).…”

Section: Discussionmentioning

confidence: 99%

Short Alternative Route for Nuclear Fuel Reprocessing Based on Organic Phase Self-Splitting

et al. 2021

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A more sustainable management of natural resources and the establishment of processes allowing a joint management of nuclear materials to avoid their diversion from their civilian use are two issues for the nuclear industry. Short alternatives to existing processes have therefore been proposed based on known systems available, tributylphosphate (TBP), for the separation of actinides by liquid/liquid extraction. Proof of concept of such alternative has been established on the uranium(VI)/thorium(IV) system. From an organic phase consisting of a mixture of TBP/n-dodecane loaded with uranium and thorium, two fluxes have been obtained: the first contains almost all of the thorium in the presence of uranium in a controlled ratio, the second contains surplus uranium. Two levers were selected to control the spontaneous separation of the organic phase: the addition of concentrated nitric acid, or the temperature variation. Best results have been obtained using a temperature drop in the liquid/liquid extraction process, and variations in process conditions have been studied. Final metal recovery and solvent recycling have also been demonstrated, opening the door for further process development.

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Third Phase Formation in the Extraction of Plutonium by Tri-n-Butyl Phosphate

Cited by 62 publications

References 5 publications

Solvent extraction studies with some fission product elements from nitric acid media employing tri-iso-amyl phosphate and tri-n-butyl phosphate as extractants

Solvent extraction studies with some fission product elements from nitric acid media employing tri-iso-amyl phosphate and tri-n-butyl phosphate as extractants

Effect of Temperature on the Extraction of Plutonium(VI) by Tri n-Amyl Phosphate

Short Alternative Route for Nuclear Fuel Reprocessing Based on Organic Phase Self-Splitting

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