Concept of spent nuclear fuel reprocessing

Степанов, С. И.; Чекмарев, А. М.

doi:10.1134/s0012500808110037

Cited by 35 publications

(11 citation statements)

References 3 publications

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“…At present, carbonate complexes of hexavalent actinides, especially uranyl, with inorganic cations were studied in rather detail in solutions and in the solid state, which is due to exclusive significance of the interaction of actinides with carbonate and bicarbonate ions in aqueous objects of the environment [3]. In future it seems possible to use the extraction process of hexavalent uranium and plutonium from carbonate solutions using methyltrialkylammonium carbonate during irradiated nuclear fuel processing [4,5]. The necessity to optimize technological tasks and behavior of nuclides in waste and in the envi-*Author for correspondence (E-mail: fedosseev@ipc.rssi.ru).…”

Section: Introductionmentioning

confidence: 98%

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH₂)₃]₄[AmO₂(CO₃)₃]·2H₂O, comparison with [C(NH₂)₃]₄[AnO₂(CO₃)₃] (An=U, Np, Pu)

et al. 2011

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Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NHSummary. A formation of Am(VI) carbonate complexes has been observed under ozonation of Am(III) in guanidinium carbonate solutions. New [C(NH 2 ) 3 ] 4 [AmO 2 (CO 3 ) 3 ]·2H 2 O tricarbonate complex has been isolated and studied by the X-ray analysis. The Am atom has oxygen environment as distorted hexagonal bipyramid with three CO 3 2− ions in equatorial plane and oxygen atoms of the AmO 2 group in the apical positions. Averaged Am−O CO 3 bond length is 2.431(13) Å, the length of Am=O bond is 1.750(12) Å. In crystal hydrogen bonds between [C(NH 2 ) 3 ] + cations, water molecules and [AmO 2 (CO 3 ) 3 ] 4− complex anions link the fragments of structure into the three-dimensional network. To compare the peculiarities of the structure of tricarbonate complexes it was prepared [C(NH 2 ) 3 ] 4 [AnO 2 (CO 3 ) 3 ], where An = U(VI), Np(VI) and Pu(VI). In structure of [C(NH 2 ) 3 ] 4 [AnO 2 (CO 3 ) 3 ] an actinide contraction appears as a slight shortening of the bond lengths in the actinyl groups AnO 2 : 1.80 Å for U, 1.78 Å for Np 1.76 Å Pu. The An−O CO 3 bond length in the equatorial plane of hexagonal bipyramids remains almost unchanged in the series from U to Am. An analysis of the structures showed that hydrogen bonding played an important role in crystal formation.

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Section: Introductionmentioning

confidence: 98%

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH₂)₃]₄[AmO₂(CO₃)₃]·2H₂O, comparison with [C(NH₂)₃]₄[AnO₂(CO₃)₃] (An=U, Np, Pu)

et al. 2011

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“…All of them are based on the use of carbonate/bicarbonate or carbonate/alkaline media. One of such methods is the CARBEX (CARBonate EXtraction) process, the concept of which was published in 2008 [5]. The most promising solvents for reprocessing of uranium from impurities from carbonate and alkaline solutions are quaternary ammonium compounds (QAC).…”

Section: Introductionmentioning

confidence: 99%

Purification of Uranium(vi) From Impurities of Fission Product Surrogates by Solvent Extraction in the Carbex Process

Frankiv¹,

Boyarintsev²,

Stepanov³

et al. 2021

RAD Conference Proceedings

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The article presents the results on the extraction and purification of uranium(VI) from impurities of surrogates of some fission products (Cr(III), Mn(IV), Cu(II), Sr(II), Cs, Sb(V), Mo(VI), Ba(II), La(III), Ce(IV), Sm(III), Eu(III), Re(V), Al(III), Y(III), Nd(III)) and Na from aqueous solutions of sodium carbonate and ammonium carbonate by solvent extraction using methyltrioctylammonium carbonate. The values of uranium purification factors were 10 3 -10 6 . Based on the carried out studies, a scheme of solvent extraction reprocessing of multicomponent carbonate solutions containing fission product surrogates was developed and optimized. This scheme showed the high efficiency of the solvent extraction technique for fractionating the fission products in the CARBEX process.

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“…In 2008, the CARBEX (CARBonate EXtraction) concept was formulated [1]. This hydrochemical method of the spent nuclear fuel (SNF) reprocessing in carbonate media using solvent extraction (SE) technique for separation and purification of uranium and plutonium from fission products (FPs).…”

Section: Introductionmentioning

confidence: 99%

Precipitative Re-Extraction of Uranium(vi) From Organic Solutions of Methyltrioctilammonium Uranyl Peroxo-Carbonate Complexes

Frankiv¹,

Boyarintsev²,

Stepanov³

2021

RAD Conference Proceedings

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The article discusses the results of the uranium(VI) re-extraction(stripping) from the methyltrioctilammonium organic phase loaded by uranium(VI) peroxo-carbonate species using ammonium carbonate and ammonium bicarbonate aqueous solutions or gaseous carbon dioxide. Conditions for 97-99% re-extraction of uranium(VI) to obtain crystalline ammonium uranyl carbonate with structure (NH4)4[UO2(CO3)3] were determined.

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Concept of spent nuclear fuel reprocessing

Cited by 35 publications

References 3 publications

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH₂)₃]₄[AmO₂(CO₃)₃]·2H₂O, comparison with [C(NH₂)₃]₄[AnO₂(CO₃)₃] (An=U, Np, Pu)

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH₂)₃]₄[AmO₂(CO₃)₃]·2H₂O, comparison with [C(NH₂)₃]₄[AnO₂(CO₃)₃] (An=U, Np, Pu)

Purification of Uranium(vi) From Impurities of Fission Product Surrogates by Solvent Extraction in the Carbex Process

Precipitative Re-Extraction of Uranium(vi) From Organic Solutions of Methyltrioctilammonium Uranyl Peroxo-Carbonate Complexes

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Concept of spent nuclear fuel reprocessing

Cited by 35 publications

References 3 publications

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH2)3]4[AmO2(CO3)3]·2H2O, comparison with [C(NH2)3]4[AnO2(CO3)3] (An=U, Np, Pu)

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH2)3]4[AmO2(CO3)3]·2H2O, comparison with [C(NH2)3]4[AnO2(CO3)3] (An=U, Np, Pu)

Purification of Uranium(vi) From Impurities of Fission Product Surrogates by Solvent Extraction in the Carbex Process

Precipitative Re-Extraction of Uranium(vi) From Organic Solutions of Methyltrioctilammonium Uranyl Peroxo-Carbonate Complexes

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Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH₂)₃]₄[AmO₂(CO₃)₃]·2H₂O, comparison with [C(NH₂)₃]₄[AnO₂(CO₃)₃] (An=U, Np, Pu)

Tricarbonate complex of hexavalent Am with guanidinium: synthesis and structural characterization of [C(NH₂)₃]₄[AmO₂(CO₃)₃]·2H₂O, comparison with [C(NH₂)₃]₄[AnO₂(CO₃)₃] (An=U, Np, Pu)