Recovery of Uranium from Wet-Process Phosphoric Acid by Extraction with Octylphenylphosphoric Acid

Hurst, F.J.; Crouse, D.J.

doi:10.1021/i260051a017

Cited by 68 publications

(26 citation statements)

References 2 publications

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“…It was shown that such synergistic systems are interesting providing that a first solvent extraction stage was implemented to concentrate uranium before the second solvent extraction stage to minimize the impurities concentration in the yellow cake (Table 7). 8 In the 1980s, COGEMA modified the Urphos process by replacing D2EHPA/TOPO by BiDiBOPP/di-n-HMOPO. 93,94 With this latter system, the uranium concentration in the extraction solvent was 4 times higher than the D2EHPA/TOPO system (Table 8).…”

Section: Other Extraction Systemsmentioning

confidence: 99%

Recovery of Uranium from Wet Phosphoric Acid by Solvent Extraction Processes

Beltrami

Cote

Mokhtari³

et al. 2014

Chem. Rev.

169

102

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Section: Other Extraction Systemsmentioning

confidence: 99%

Recovery of Uranium from Wet Phosphoric Acid by Solvent Extraction Processes

Beltrami

Cote

Mokhtari³

et al. 2014

Chem. Rev.

169

102

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“…In case of LEM methods also, the limitations of solvent extraction appear to be alleviated due to lower metal ion loading which is a consequence of simultaneous stripping. Interestingly, plant scale separations of U from phosphoric acid feeds have been demonstrated using LEM methods (29,30). We have reported Am recovery from weakly acidic feed solutions by LEM using PC88A (2-ethylexyl hydrogen 2-ethylhexyl phosphonate) and HD2EHP (di-2-ethylhexylphosphoric acid) as the carrier extractants (31,32).…”

Section: Please Scroll Down For Articlementioning

confidence: 99%

A Novel Liquid Emulsion Membrane Containing TODGA as the Carrier Extractant for Am Recovery from Acidic Wastes

Kandwal¹,

Mohapatra²

2013

Separation Science and Technology

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The recovery of Am has been investigated by Liquid Emulsion Membrane (LEM) containing 0.1 M N,N,N 0 ,N 0 -tetraoctyl-3-oxapentane diamide (TODGA) þ 0.5 M di-n-hexyloctanamide (DHOA) in n-dodecane as extractant. Span 80 (sorbitan monooleate) was used as the surfactant for making the emulsion while 3 M HNO 3 and 0.1 M acetate buffer (at pH 4.75) were used as the external and internal phases, respectively. Optimized conditions indicated 2% Span 80 was required for making the emulsions. The effect of different experimental conditions such as varying feed acidity, varying volume ratio, different strippants, and varying TODGA concentration have been studied for the quantitative removal of Am from acidic solution. The higher transport rate has been observed which can be attributed to the higher surface area per unit volume available for mass transport. Demulsification was possible by heating the emulsions to 80 C.Actual acidic radioactive waste has also been tested for the recovery of americium. The results show the applicability of ELM for the removal of Am(III) from waste solutions with a faster rate of transport as compared to those reported previously.

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“…The modeling equation for the organic tank considered as the ideal stirred vessel is the same as that in the previous model (eq 11). In the first model, A is the parameter that describes the equilibrium relationship of the extraction defined by eq 8.…”

Section: Stripping Modulementioning

confidence: 99%

An Integrated Process for the Removal of Cd and U from Wet Phosphoric Acid

Ortíz

Alonso

Urtiaga

et al. 1999

Ind. Eng. Chem. Res.

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In this work, an integrated process based on the application of two membrane technologies for the selective recovery of the U and the Cd contained in wet phosphoric acid is presented. The process is based on the removal of U by ion exchange using the Purolite S940 resin as ionexchange resin followed by the selective removal of Cd by means of membrane-assisted solvent extraction with Aliquat 336 as the selective extractant. After sorption of U, the elution step was carried out with a 1 M solution of Na 2 CO 3 whereas the back extraction of Cd was efficiently achieved by simply using water in the back-extraction phase. Because of working with acidic solutions containing initially 200 mg/L of U and 50 mg/L of Cd, the viability of the process for reduction of the U and Cd concentration below 2 mg/L has been checked, obtaining the kinetic models and parameters of the removal steps, thus, establishing the basis for the process design and optimization.

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Recovery of Uranium from Wet-Process Phosphoric Acid by Extraction with Octylphenylphosphoric Acid

Cited by 68 publications

References 2 publications

Recovery of Uranium from Wet Phosphoric Acid by Solvent Extraction Processes

Recovery of Uranium from Wet Phosphoric Acid by Solvent Extraction Processes

A Novel Liquid Emulsion Membrane Containing TODGA as the Carrier Extractant for Am Recovery from Acidic Wastes

An Integrated Process for the Removal of Cd and U from Wet Phosphoric Acid

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