Reduction of Pu(IV) by carbohydrazide in aqueous solutions and in two-phase systems with tributyl phosphate

Alekseenko, V. N.; Dvoeglazov, K. N.; Marchenko, V. I.; Alekseenko, S. N.; Volk, V. I.; Podrezova, L. N.

doi:10.1007/s10967-014-3882-7

Cited by 9 publications

(5 citation statements)

References 6 publications

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“…One of specific features of the reaction of Pu(IV) with carbohydrazide is stronger, compared to other SHs, dependence of the rate on the solution acidity (the order with respect to HNO 3 is -3 [28]). Therefore, its use for stripping Pu from a TBP solution is the most efficient at low acidity (≤1 M HNO 3 ).…”

Section: Substituted Hydrazinesmentioning

confidence: 96%

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Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Marchenko

Alekseenko²,

Dvoeglazov

2015

Radiochemistry

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Scientific, technical, and patent information on the use of organic compounds as reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing is summarized and correlated. Organic derivatives of hydrazine and hydroxylamine, and also oximes and urea derivatives at relatively low acidities and temperatures reduce Np(VI) to Np(V) and Pu(IV) to Pu(III). As the acidity and temperature are increased, Np(V) is slowly reduced to Np(IV). Alcohols, aldehydes, hydrocarbons, and acetic acid were identified among products of oxidation of the organic compounds in nitric acid medium. The above-named organic reductants can be used in different steps of the PUREX process: separation of Pu and Np from U in the first extraction cycle, purification of U to remove Np in the second cycle of uranium purification, and Pu stripping in the step of its final purification. Laboratory experiments performed on countercurrent extraction installations of mixersettlers and of centrifugal contactors demonstrated the possibility of reaching high separation factors of U from Pu and/or Np and high degrees of plutonium concentration to obtain Pu strips containing up to 150 g L -1 Pu.

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Section: Substituted Hydrazinesmentioning

confidence: 96%

“…One of these experiments involved reductive stripping of Pu with its separation from U under the conditions of the first extraction cycle on an 8-step CC block [28,41]. The initial solvent product had the following composition: U 105 g L -1 , Pu 1.0 g L -1 , Np 148 mg L -1 , and Tc 134 mg L -1 .…”

Section: Substituted Hydrazinesmentioning

confidence: 99%

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Marchenko

Alekseenko²,

Dvoeglazov

2015

Radiochemistry

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“…CBZ not only has a strong coordination ability with metal ions, but it is also a common antioxidant and stabilizer. [35,36] Therefore, CBZ was used as a bifunctional additive to control the crystallization rate of CsSnI 3 and the reduction of Sn 4+ to Sn 2+ during perovskite growth.…”

Section: Bifunction Of Cbzmentioning

confidence: 99%

A Bifunctional Carbazide Additive For Durable CsSnI₃ Perovskite Solar Cells

et al. 2023

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Inorganic CsSnI 3 with low toxicity and a narrow bandgap is a promising photovoltaic material. However, the performance of CsSnI 3 perovskite solar cells (PSCs) is much lower than that of Pb-based and hybrid Sn-based (e.g., CsPbX 3 and CH(NH 2 ) 2 SnX 3 ) PSCs, which may be attributed to its poor film-forming property and the deep traps induced by Sn 4+ . Here, a bifunctional additive carbazide (CBZ) is adapted to deposit a pinhole-free film and remove the deep traps via two-step annealing. The lone electrons of the -NH 2 and -CO units in CBZ can coordinate with Sn 2+ to form a dense film with large grains during the phase transition at 80 °C. The decomposition of CBZ can reduce Sn 4+ to Sn 2+ during annealing at 150 °C to remove the deep traps. Compared with the control device (4.12%), the maximum efficiency of the CsSnI 3 :CBZ PSC reaches 11.21%, which is the highest efficiency of CsSnI 3 PSC reported to date. A certified efficiency of 10.90% is obtained by an independent photovoltaic testing laboratory. In addition, the unsealed CsSnI 3 :CBZ devices maintain initial efficiencies of ≈100%, 90%, and 80% under an inert atmosphere (60 days), standard maximum power point tracking (650 h at 65 °C), and ambient air (100 h), respectively.

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“…As a stationary phase, an aqueous solution which comprises a balanced mixture of reductants was used, one of which (carbohydrazide) had the best kinetic parameters for Pu(IV)→Pu(III) reduction, the other (diformylhydrazine) -for Tc (VII)→Tc (IV) reduction [6,7,8].…”

Section: U-extract Purification From Pu and Tcmentioning

confidence: 99%

The Development of the Liquid Chromatography Process for the Spent Nuclear Fuel Reprocessing Technology

Podrezova¹,

Volk²,

Dvoeglazov³

et al. 2017

RadJ

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Abstract. In spent nuclear fuel (SNF) reprocessing technology, the hydrometallurgical scheme in the version of the classic PUREX process was today accepted. However, in this case mass-transfer operations require significant aqueous flows. The volume of these streams subsequently becomes a liquid radioactive waste (LRW). The reducing of the waste solutions volume in the general SNF recycling process, with the following minimizing of LRW volume, was based on the use of alternative mass-transfer process -liquid chromatography (LC). Uranium-plutonium extract purification by LC process in the simulating SNF reprocessing process was carried out. The dynamic experiments on a laboratory glass column packed with a porous granular high surface material were successfully performed, and the effectiveness of the purification process was evaluated. On the laboratory liquid chromatography column (LCC), a series of dynamic experiments were carried out in order to obtain the original data for the design of a pilot unit.

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Reduction of Pu(IV) by carbohydrazide in aqueous solutions and in two-phase systems with tributyl phosphate

Cited by 9 publications

References 6 publications

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

A Bifunctional Carbazide Additive For Durable CsSnI₃ Perovskite Solar Cells

The Development of the Liquid Chromatography Process for the Spent Nuclear Fuel Reprocessing Technology

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Reduction of Pu(IV) by carbohydrazide in aqueous solutions and in two-phase systems with tributyl phosphate

Cited by 9 publications

References 6 publications

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

A Bifunctional Carbazide Additive For Durable CsSnI3 Perovskite Solar Cells

The Development of the Liquid Chromatography Process for the Spent Nuclear Fuel Reprocessing Technology

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Product

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A Bifunctional Carbazide Additive For Durable CsSnI₃ Perovskite Solar Cells