Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model

Пузиков, Е. А.; Кудинов, А. С.; Blazheva, I. V.; Sytnik, L. V.; Shishkin, D. N.; Голецкий, Н. Д.; Zilberman, B. Ya.

doi:10.1134/s1066362217020060

Cited by 7 publications

(4 citation statements)

References 7 publications

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“…The first studies of extraction processes began in the 1960s based on bulky mixer-settlers with low kinetics and low specific productivity. In the 1970s, pulsating columns were developed, as a result, several apparatuses were created for the implementation of rare metal extraction processes [7]. Large volumes of flammable-explosive extractant in the cycle required serious costs to ensure production safety.…”

Section: Introductionmentioning

confidence: 99%

Physical and Chemical Foundations of the Technology for Obtaining Uranium Oxides

Mukhachev¹,

Yelatontsev²,

Kharitonova³

2022

Problems of Atomic Science and Technology

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The article presents the results of industrial testing of processes for obtaining high-purity uranium compounds, including extraction, concentration, and purification of uranium from a mixture of nitric and phosphoric acids, solid-phase stripping, and reduction of U(VI) to U(IV). It is shown that the combination of three different extraction lines for the concentration and purification of uranium from accompanying valuable elements and radioactive isotopes makes it possible to obtain a natural uranium concentrate with a low content of impurities, which determine the economics of uranium hexafluoride production. The processes of drying and roasting of crystals of ammonium uranyl tricarbonate after solid-phase re-extraction in an atmosphere of reducing gases of ammonia and hydrogen make it possible to obtain uranium dioxide suitable for fluorination to obtain tetra and uranium hexafluoride.

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Section: Introductionmentioning

confidence: 99%

Physical and Chemical Foundations of the Technology for Obtaining Uranium Oxides

Mukhachev¹,

Yelatontsev²,

Kharitonova³

2022

Problems of Atomic Science and Technology

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“…The model of Asakura et al was used in JAERI’s PARC code and also in later simulations . In Russia, Puzikov and co-workers ,,, also proposed methods based on the ligand exchange mechanism, as well as more complex reactions in the calculation. , …”

Section: Introductionmentioning

confidence: 99%

“…The model of Asakura et al was used in JAERI's PARC code 23 and also in later simulations. 38 In Russia, Puzikov and co-workers 20,55,15,21 also proposed methods based on the ligand exchange mechanism, as well as more complex reactions in the calculation. 15,21 In contrast, some researchers developed models based on the coextraction mechanism to calculate the distribution coefficient from aqueous concentrations and free TBP in the organic phase, rather than from the organic uranium concentration.…”

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confidence: 99%

Distribution Coefficient Model for Zirconium and Technetium Extraction from Nitric Acid Solution

Chen

Jobson

Taylor

et al. 2021

Ind. Eng. Chem. Res.

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Technetium and zirconium are two of the most problematic fission products in the PUREX process due to their complex extraction behaviors. Although there are several published works related to the calculation of Tc and Zr distribution coefficients, the reliability of those methods must be validated carefully, and further knowledge in this area is still needed. This work is, therefore, devoted to developing technetium and zirconium distribution coefficient models for predicting their distribution between nitric acid solution and tributyl phosphate in diluent for solutions containing uranium, technetium, and zirconium. The distribution coefficient model for zirconium is based on the organic nitric acid concentration, rather than the free TBP concentration. An improved technetium distribution coefficient model, in the absence of other metals, is also developed. The coextraction of technetium and zirconium or uranium is calculated by ligand exchange mechanisms. The validation results demonstrate that the distribution coefficient models developed in this work are more accurate than established models.

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“…The main advantage of these diluents was their higher density than water, because at high separated metal loadings the density of solvents based on diluents with low density can exceed the density of the aqueous phase which results in the reversal of the phases and severe complications of the separation processes. However, those chlorinated hydrocarbons such as hexachlorobutadiene, tetrachloroethylene or tetrachloromethane were found to suffer from different disadvantages such as corrosion problems, toxicity of the off-gasses, and volatility [7,8]. They were also found to be sensitive to ionizing radiation with some degradation products being miscible with or soluble in aqueous phase.…”

Section: Introductionmentioning

confidence: 99%

Fluorinated Carbonates as New Diluents for Extraction and Separation of f-Block Elements

Distler

Mindova

John

et al. 2020

Solvent Extraction and Ion Exchange

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The fluorinated carbonate BK-1 solvent was studied as a diluent in extraction systems with different extracting agents -CMPO, THDGA, CyMe4-BTBP and CyMe4-BTPhen, which are the most promising molecules for separation of minor actinides and lanthanides. Dependence of the extraction properties of the system on the concentrations of HNO3 or extracting compound, kinetics of trivalent metal extraction and extraction of the ions by neat diluent (without the addition of extracting agent) were investigated. Based on the obtained results, BK-1 is a promising candidate diluent for fblock metal separation.

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Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model

Cited by 7 publications

References 7 publications

Physical and Chemical Foundations of the Technology for Obtaining Uranium Oxides

Physical and Chemical Foundations of the Technology for Obtaining Uranium Oxides

Distribution Coefficient Model for Zirconium and Technetium Extraction from Nitric Acid Solution

Fluorinated Carbonates as New Diluents for Extraction and Separation of f-Block Elements

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