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Zilberman, B. Ya.; Akhmatov, A. A.; Saprykin, V. F.; Sytnik, L. V.; Gostinin, G. I.

doi:10.1023/a:1012815315175

Cited by 3 publications

(5 citation statements)

References 2 publications

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“…The use of peracetic acid CH 3 COOOH as stripping agent appeared to be more successful. In this case, the degree of the Np stripping exceeded 99% without noticeable transfer of U and Pu into the aqueous phase [35].…”

Section: Substituted Hydrazinesmentioning

confidence: 83%

“…A distinctive feature of these reagents is that they exhibit not only reducing but also complexing properties with respect to tetravalent acti-nides [62,63]. FHA and AHA in aqueous solutions tend to undergo acid hydrolysis yielding hydroxylamine and the corresponding carboxylic acid (HCOOH or CH 3 COOH).…”

Section: Hydroxamic Acidsmentioning

confidence: 99%

“…Plutonium(IV) is reduced slowly, and the reduction rate decreases as the acidity and AHA concentration are increased [62,71]. It was initially assumed [72,73] that the species that actually reduces Pu(IV) is another product of AHA hydrolysis, hydroxylamine, but later studies showed that, most probably, the reactive species is AHA itself [74].…”

Section: Hydroxamic Acidsmentioning

confidence: 99%

“…Despite low rate of the Pu reduction, its stripping with AHA is relatively complete owing to the formation of strong hydrophilic complexes of Pu(IV) with AHA [62,63,76,77]. High rate of the Np(VI) reduc-tion with this reagent and, apparently, no less high rate of its complexation with Pu(IV) and Np(IV) allow the use of AHA both for joint stripping of Pu and Np to separate them from U and for the U decontamination from each of these elements in CC; in the process, Np can be initially present in the organic phase in both hexa-and tetravalent state.…”

Section: Hydroxamic Acidsmentioning

confidence: 99%

See 3 more Smart Citations

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: 83%

Section: Hydroxamic Acidsmentioning

confidence: 99%

Section: Hydroxamic Acidsmentioning

confidence: 99%

Section: Hydroxamic Acidsmentioning

confidence: 99%

See 2 more Smart Citations

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

Marchenko

Alekseenko²,

Dvoeglazov

2015

Radiochemistry

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“…Moreover, solutions of 0.2 M hydrazinium and hydroxylammonium were used as anti-nitrous reagents to keep uranium and neptunium in their tetravalent oxidation state during the hydrothermal treatment. We checked that both compounds slowly decomposed in hot nitric media. , …”

Section: Methodsmentioning

confidence: 99%

Hydrothermal Method of Preparation of Actinide(IV) Phosphate Hydrogenphosphate Hydrates and Study of Their Conversion into Actinide(IV) Phosphate Diphosphate Solid Solutions

2007

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Several compositions of Th2-x/2AnIVx/2(PO4)2(HPO4).H2O (An=U, Np, Pu) were prepared through hydrothermal precipitation from a mixture of nitric solutions containing cations and concentrated phosphoric acid. All the samples were fully characterized by X-ray diffraction, UV-vis, and infrared spectroscopies to check for the existence of thorium-actinide(IV) phosphate hydrogenphosphate hydrates solid solutions. Such compounds were obtained as single phases, up to x=4 for uranium, x=2 for neptunium, and x<4 for plutonium, the cations being fully maintained in the tetravalent oxidation state. In a second step, the samples obtained after heating crystallized precursors at high temperature (1100 degrees C) were characterized. Single-phase thorium-actinide(IV) phosphate-diphosphate solid solutions were obtained up to x=0.8 for Np(IV) and x=1.6 for Pu(IV). For higher substitution rates, polyphase systems composed by beta-TAnPD, An2O(PO4)2, and/or alpha-AnP2O7 were formed. Finally, this hydrothermal route of preparation was applied successfully to the synthesis of an original phosphate-based compound incorporating simultaneously tetravalent uranium, neptunium and plutonium.

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Isolation of Separated Waste of Nuclear Industry

Yudintsev

2021

Radiochemistry

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Untitled

Cited by 3 publications

References 2 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

Hydrothermal Method of Preparation of Actinide(IV) Phosphate Hydrogenphosphate Hydrates and Study of Their Conversion into Actinide(IV) Phosphate Diphosphate Solid Solutions

Isolation of Separated Waste of Nuclear Industry

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