CARBEX process, a new technology of reprocessing of spent nuclear fuel

Степанов, С. И.; Boyarintsev, A. V.; Vazhenkov, M. V.; Myasoedov, Β. F.; Nazarov, E. O.; Сафиулина, А. М.; Тананаев, И. Г.; So, Hen Vin; Чекмарев, А. М.; Civadze, A. Yu.

doi:10.1134/s1070363211090404

Cited by 28 publications

(15 citation statements)

References 13 publications

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“…[2] Для переработки ОЯТ предложен КАРБЭКСпроцесс, основанный на селективном переводе урана и плутония в карбонатный раствор с последующей их очисткой от продуктов деления экстракцией солями четвертичных аммониевых оснований. [3] Щелочной высокоактивный рафинат КАРБЭКС-процесса с большим содержанием карбоната натрия потребуется перерабатывать, скорее всего, путем экстракционного фракционирования. Таким образом, очевидна потребность в эффективных методах фракционирования щелочных ВАО.…”

Section: Introductionunclassified

Americium and Cesium Extraction from Alkaline Media by Calix[8]arenes with p-tert-Butyl and Isononyl Substituents on the Upper Rim: Aggregation Effect

Смірнов

Stepanova

Tyupina³

et al. 2017

MHC

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На основе промышленно доступного изононилфенола синтезированы и охарактеризованы каликс[8]арены с различным соотношением трет-бутильных и изононильных групп на верхнем ободе макроцикла. Изучена экстракция 137 Cs и 241 Am из карбонатно-щелочных сред растворами синтезированных п-алкилкаликс[8] аренов в тетрахлорэтилене. Установлена зависимость коэффициентов распределения от рН водной фазы в интервале от 11 до 13.9 и соотношения трет-бутильных и изононильных групп в каликсареновой платформе. Определен состав экстрагируемых сольватов цезия и америция с синтезированными каликс[8]аренами. Показано, что в щелочных средах радионуклиды эффективнее экстрагируются трет-бутилкаликс[8]ареном и его производным, содержащим две изононильные группы на верхнем ободе макроцикла. Они образуют в органической фазе агрегаты диаметром 8.0±1.2 нм, тогда как каликс[8]арены, содержащие 50 % и более изононильных заместителей, существуют в органической фазе в мономерной форме и существенно хуже экстрагируют исследованные радионуклиды.

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Section: Introductionunclassified

Americium and Cesium Extraction from Alkaline Media by Calix[8]arenes with p-tert-Butyl and Isononyl Substituents on the Upper Rim: Aggregation Effect

Смірнов

Stepanova

Tyupina³

et al. 2017

MHC

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“…The evaluation of different extractants and diluents were investigated at different times. The experimental data of extraction of surrogates at various time (3,10,15, 20 and 30 min) using different organic solvents are reported in Tables 1, 2, 3, 4 and 5. These results show the best combination of extractants and diluents at various times.…”

Section: Phase 1: Evaluation Of the Organic Solvent Using Surrogatesmentioning

confidence: 99%

“…Aliquat 336 in xylene, kerosene and toluene was selected for the extraction of uranium from alkaline solutions as it is a quaternary amine reagent shown to be a successful extractant from carbonate media by Stepanov et al [10]. It is an ionic liquid reagent similar to Alamine 336.…”

Section: Phase 1: Evaluation Of the Organic Solvent Using Surrogatesmentioning

confidence: 99%

“…The authors reported that over 90% of uranium was stripped from loaded organic solution. Stepanov et al [10] studied a new technology that can be used for reprocessing of spent nuclear fuel, the so called CARBEX (carbonate extraction) process. The same workers reported that CARBEX process can be more effective and safe than PUREX process.…”

Section: Introductionmentioning

confidence: 99%

“…hydrogen peroxide. Stepanov et al [10] stated that carbonate solutions differ from acid leach solutions because they do not show oxidative activity when there are no oxidants. Therefore, oxidants are needed for an effective dissolution of uranium dioxide in carbonate solution.…”

Section: Introductionmentioning

confidence: 99%

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Organic solvent extraction of uranium from alkaline nuclear waste

Mathuthu

Mokhine

Stassen

2019

J Radioanal Nucl Chem

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There are proliferation issues with the Plutonium Uranium Redox Extraction process due to the possibility of recovering plutonium. The objective of this research was to evaluate different organic extraction ligands that can remove uranium from the nuclear waste and to determine the most effective organic solvent for extracting uranium only, from alkaline media. The results indicate that Alamine 336 in xylene has zero (0%) extraction capability for surrogate fission products at an optimum extraction time of 15 min. Aliquat 336 in xylene has an extraction percentage of 72% for uranium in 60 min. However, Aliquat 336 in toluene extracted 82% of the uranium from the feed solution after 30 min, decreasing to 76% after 60 min.

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Photochemical Synthesis and Characterization of a Uranyl Peroxide Triethylamine N‐Oxide Dimer

Lottes,

Carter

2024

Eur J Inorg Chem

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A µ‐peroxido‐bis[di‐triethylamine N‐oxide‐dichloro‐dioxouranium] complex with the formula [(UO2)2O2(ON(CH2CH3)3)4Cl2] (complex 1) was synthesized photochemically from a reaction containing uranyl chloride, triethylamine, and H2O2. The photochemical breakdown of H2O2 yielded •OH radicals that reacted with triethylamine to form triethylamine N‐oxide (TEAO) in situ, which subsequently coordinated to UO22+ cations in a monodentate fashion via the N‐oxide functional groups. Structure determination using single crystal X‐ray diffraction revealed that TEAO ligands also formed intermolecular and intramolecular hydrogen bonds with UO22+ and peroxide moieties, and the intermolecular H‐bonding interactions displayed a temperature dependence with Oyl ‐ ‐ H – C and Oper ‐ ‐ H – C distances shortening at 100(2) K by ca. 0.1 Å. Raman spectroscopy data were collected on single crystals of 1 and peak fitting of these results allowed for assignments of peaks including C‐N stretches for TEAO ligands bound to UO22+ cations at 696.8 cm‐1, 717.8 cm‐1, and 776.5 cm‐1, which are redshifted by approximately 30 cm‐1 when compared to free triethylamine. UO22+ν1 and O22‐ν1 stretches, U‐Oper stretches, and notably, U‐Cl stretches were all identified as well, with U‐Cl modes at 198.9 cm‐1 and 212.1 cm‐1 substantially redshifted compared to the uranyl chloride starting material.

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CARBEX process, a new technology of reprocessing of spent nuclear fuel

Cited by 28 publications

References 13 publications

Americium and Cesium Extraction from Alkaline Media by Calix[8]arenes with p-tert-Butyl and Isononyl Substituents on the Upper Rim: Aggregation Effect

Americium and Cesium Extraction from Alkaline Media by Calix[8]arenes with p-tert-Butyl and Isononyl Substituents on the Upper Rim: Aggregation Effect

Organic solvent extraction of uranium from alkaline nuclear waste

Photochemical Synthesis and Characterization of a Uranyl Peroxide Triethylamine N‐Oxide Dimer

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