UO2, NpO2 and PuO2 preparation in aqueous nitrate solutions in the presence of hydrazine hydrate

Kulyako, Yu. M.; Перевалов, С. А.; Trofimov, T. I.; Malikov, D. A.; Винокуров, С. Е.; Samsonov, M. D.; Myasoedov, Β. F.; Федосеев, А. М.; Bessonov, A. A.; Shadrin, A. Yu.

doi:10.1007/s10967-013-2756-8

Cited by 8 publications

(6 citation statements)

References 7 publications

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“…As we showed previously [1][2][3], hydrated uranium dioxide UO 2 ·nH 2 O prepared in UO 2 (NO 3 ) 2 solutions in the presence of hydrazine hydrate (HH) at ~90°С in 48 h in the course of subsequent heat treatment in an electrical resistance furnace transforms into various oxides depending on the conditions: into UO 2 in an inert or reducing atmosphere in the interval 280-800°С, into UO 3 in air at 440°С, and into U 3 O 8 in the interval 570-800°С. The drawbacks of this process are the presence of residual mother liquors and relatively low rate of the transformation of UO 2 (NO 3 ) 2 into UO 2 ·nH 2 O.…”

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confidence: 68%

Preparation of uranium oxides by reductive denitration of uranyl nitrate under microwave heating

et al. 2015

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Autoclave denitration of solid uranyl nitrate in the presence of hydrazine hydrate at 120°С under the action of microwave radiation (MWR) leads to the formation of uranium dioxide with simultaneous breakdown of excess hydrazine hydrate and nitrate ions. The reaction yields UO 2 when performed in an open system in a reducing medium and U 3 O 8 when performed under the conditions of contact with air. Thus, principles have been developed for a new, virtually waste-free procedure for the synthesis of uranium dioxide for the subsequent preparation of oxide nuclear fuel. The procedure is characterized by high rate and considerably reduced power consumption, compared to the similar process performed with convective heating.

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confidence: 68%

Preparation of uranium oxides by reductive denitration of uranyl nitrate under microwave heating

et al. 2015

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“…For smaller scale, µg reactions, calcination of ion-exchange resins is also possible [179]. Synthesis of polycrystalline samples of actinide oxides have also been reported through sol-gel [53] and aqueous routes [72,124,130]. Many of the actinide oxides can be hypo-or hyperstoichiometric, i.e.…”

Section: Crystal Growthmentioning

confidence: 99%

Crystal structure and magnetism of actinide oxides: a review

Rai,

Bretaña,

Morrison

et al. 2024

Rep. Prog. Phys.

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In actinide systems, the 5f electrons experience a uniquely delicate balance of effects and interactionshaving similar energy scales, which are often difficult to properly disentangle. The interplayof factors such as the dual character of 5f-states, competing interactions, and strong spin-orbit couplingresults in magnetically unusual and intriguing behavior: multi-k antiferromagnetic ordering,multipolar ordering, mixed valence configurations, and more. Despite the inherent allure of theirexotic properties, the exploratory science of even the more basic, binary systems like the actinideoxides has been extremely limited due to their toxicity, radioactivity, and reactivity. In this article,we provide an overview of the available synthesis techniques for selected binary actinide oxides,including the actinide dioxides, sesquioxides, and a selection of the higher oxides. For these oxides,we review and evaluate the current state of knowledge on their crystal structures and magneticproperties. In many aspects, substantial knowledge gaps exist in the current body of research onactinide oxides related to understanding their magnetic ground states. Bridging these gaps is vitalfor improving not only a fundamental understanding of these systems but also of future nucleartechnologies. To this end, we note the experimental techniques and necessary future investigationswhich may aid in better elucidating the nature of these fascinating systems.

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“…To avoid accumulation of fluoride in the bottoms, the process should be performed under strongly acidic conditions [25] at reduced residual pressure to decrease the temperature and thus to avoid intense corrosion of tubes of the heating chamber. The bottoms are continuously fed from the evaporator to final evaporator to distill off the residual amounts of hydrofluoric acid by steam treatment on plates, with the subsequent delivery to the HLW calcination unit.…”

Section: Concentration Of Process Hlw and Recycled Ilwmentioning

confidence: 99%

РH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor

et al. 2016

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A technology for reprocessing mixed uranium-plutonium nitride fiel (MUPN) from BREST reactor is considered. The technology should ensure reprocessing of spent nuclear fuel with the storage time after irradiation of no more than 1 year, 10-15% content of fissile materials (FM), and burn-up of 10% of heavy atoms. The target product of the technology is a mixture of actinide oxides separated from fission products with the separation factor of ~10 6 . A PH (Pyro-Hydro) process was suggested for MUPN SNF reprocessing. It involves pyroelectrochemical fuel reprocessing with separation of U, Np, and Pu from the major fraction of fission products responsible for the heat release from the fuel and for the radiation load on process media, a series of hydrometallurgical operations for final purification of the target products (U-Pu-Np-Am), and radioactive waste (RW) management. The PH process is being developed since 2011 by the teams from the Bochvar High-Tech

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UO2, NpO2 and PuO2 preparation in aqueous nitrate solutions in the presence of hydrazine hydrate

Cited by 8 publications

References 7 publications

Preparation of uranium oxides by reductive denitration of uranyl nitrate under microwave heating

Preparation of uranium oxides by reductive denitration of uranyl nitrate under microwave heating

Crystal structure and magnetism of actinide oxides: a review

РH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor

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