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Effect of High-temperature VVER-1000 SNF Reprocessing Time on the Extent of Fission Product Removal

Radiochemistry (New York, N.Y.), 2024-04, Vol.66 (2), p.156-162

2024

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Ceramics Based on the NaRe2(PO4)3 Phosphate with the Kosnarite Structure as Waste Forms for Technetium Immobilization

Inorganic materials, 2022-03, Vol.58 (3), p.325-332

2022

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Denitration of radioactive waste with formaldehyde during evaporation in the natural-circulation evaporator

IOP conference series. Earth and environmental science, 2021-09, Vol.864 (1), p.12046

2021

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Nitric acid adduct formation during crystallization of barium and strontium nitrates and their co-precipitation from nitric acid media

Journal of radioanalytical and nuclear chemistry, 2015-04, Vol.304 (1), p.387-393

2015

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Development, analysis, and simulation of a technological structure for reprocessing irradiated nuclear fuel from nuclear power plants by water-extraction methods

Atomic energy (New York, N.Y.), 2009-11, Vol.107 (5), p.333-347

2009

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Beyond-design-basis regimes of uranium stripping and of carbonate regeneration of the solvent

Radiochemistry (New York, N.Y.), 2017-11, Vol.59 (6), p.587-595

2017

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Simulation of the dynamic beyond-design-basis regime in an extraction–scrubbing unit consisting of mixer–settlers or centrifugal contactors in reprocessing spent nuclear fuel from nuclear power plants and of impurex process

Radiochemistry (New York, N.Y.), 2017-09, Vol.59 (5), p.469-481

2017

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Interaction of thorium and plutonium with pertechnetic acid in the course of extraction from nitric acid solutions with tributyl phosphate in diluent and its mathematical description

Radiochemistry (New York, N.Y.), 2016-07, Vol.58 (4), p.374-380

2016

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Preliminary studies of dynamic regimes in the extraction-scrubbing groups of units of the experimental and demonstration center (EDC) using mathematical modeling

Radiochemistry (New York, N.Y.), 2014-11, Vol.56 (6), p.583-592

2014

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Preparation of Tc-NpO2 metal-ceramic compositions and their imitators (Re, Th, Nd) for long-term safe storage of long-life fission products

Journal of nuclear materials, 2023-12, Vol.587, p.154711, Article 154711

2023

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Batching of spent AMB nuclear fuel for reprocessing at the industrial association mayak

Atomic energy (New York, N.Y.), 2013-09, Vol.114 (5), p.344-354

2013

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Effect of high-temperature VVER-1000 SNF processing duration on the extent of fission product removal

Радиохимия, 2024-09, Vol.66 (2)

2024

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Localization of fluoride ion at LRW by evaporation in a pilot plant

AIP Conference Proceedings, 2021, Vol.2388 (1)

2021

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A New Approach to Simulation of Extraction Equilibria in the PUREX Process

Solvent extraction and ion exchange, 2015-06, Vol.33 (4), p.362-384

2015

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Modernizing the design of mold sleeves for casting circular semifinished products

Metallurgist (New York), 2009, Vol.53 (1-2), p.81-84

2009

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Testing of the technology and equipment for treatment of ILW and HLW generated by extraction reprocessing of NPP spent fuel

AIP conference proceedings, 2017, Vol.1886 (1)

2017

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Influence of pressure (temperature) on the nitric acid distribution between the liquid and vapor in the course of evaporation of nitric acid radioactive waste

Radiochemistry (New York, N.Y.), 2016-05, Vol.58 (3), p.237-242

2016

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Effect of salting-out agents on nitric acid distribution between liquid and vapor in the course of evaporation of nitric acid radioactive waste

Radiochemistry (New York, N.Y.), 2016-03, Vol.58 (2), p.149-158

2016

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Interaction of zirconium with pertechnetic acid in the course of extraction from nitric acid solutions with tributyl phosphate in diluent in the presence of uranyl nitrate at various temperatures and its mathematical description

Radiochemistry (New York, N.Y.), 2015-05, Vol.57 (3), p.273-284

2015

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Radiation resistance of hydrocarbon diluents of tributyl phosphate in a two-phase system and carbonate regeneration of the solvent

Radiochemistry (New York, N.Y.), 2015-03, Vol.57 (2), p.143-151

2015

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Influence of temperature on the extraction of actinides from nitric acid solutions into 30% TBP: Description within the framework of a new model

Radiochemistry (New York, N.Y.), 2015-03, Vol.57 (2), p.136-142

2015

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Hydrometallurgical Reprocessing of BREST-OD-300 Mixed Uranium-plutonium Nuclear Fuel

Procedia chemistry, 2016, Vol.21, p.148-155

2016

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Ways of technetium and neptunium localization in extraction reprocessing of spent nuclear fuel from nuclear power plants

Radiochemistry (New York, N.Y.), 2014-09, Vol.56 (5), p.501-514

2014

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Mathematical description of the extraction of impurity acids with tributyl phosphate in diluent and of the coextraction of the acid anions with uranyl nitrate

Radiochemistry (New York, N.Y.), 2014-03, Vol.56 (2), p.167-172

2014

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Liquid-vapor distribution of acids in HNO3-H2O and HNO3-H2O-HA systems in evaporators

Theoretical foundations of chemical engineering, 2011-08, Vol.45 (4), p.530-536

2011

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Effect of High-temperature VVER-1000 SNF Reprocessing Time on the Extent of Fission Product Removal

Ceramics Based on the NaRe2(PO4)3 Phosphate with the Kosnarite Structure as Waste Forms for Technetium Immobilization

Denitration of radioactive waste with formaldehyde during evaporation in the natural-circulation evaporator

Nitric acid adduct formation during crystallization of barium and strontium nitrates and their co-precipitation from nitric acid media

Development, analysis, and simulation of a technological structure for reprocessing irradiated nuclear fuel from nuclear power plants by water-extraction methods

Beyond-design-basis regimes of uranium stripping and of carbonate regeneration of the solvent

Simulation of the dynamic beyond-design-basis regime in an extraction–scrubbing unit consisting of mixer–settlers or centrifugal contactors in reprocessing spent nuclear fuel from nuclear power plants and of impurex process

Interaction of thorium and plutonium with pertechnetic acid in the course of extraction from nitric acid solutions with tributyl phosphate in diluent and its mathematical description

Preliminary studies of dynamic regimes in the extraction-scrubbing groups of units of the experimental and demonstration center (EDC) using mathematical modeling

Preparation of Tc-NpO2 metal-ceramic compositions and their imitators (Re, Th, Nd) for long-term safe storage of long-life fission products

Batching of spent AMB nuclear fuel for reprocessing at the industrial association mayak

Effect of high-temperature VVER-1000 SNF processing duration on the extent of fission product removal

Localization of fluoride ion at LRW by evaporation in a pilot plant

A New Approach to Simulation of Extraction Equilibria in the PUREX Process

Modernizing the design of mold sleeves for casting circular semifinished products

Testing of the technology and equipment for treatment of ILW and HLW generated by extraction reprocessing of NPP spent fuel

Influence of pressure (temperature) on the nitric acid distribution between the liquid and vapor in the course of evaporation of nitric acid radioactive waste

Effect of salting-out agents on nitric acid distribution between liquid and vapor in the course of evaporation of nitric acid radioactive waste

Interaction of zirconium with pertechnetic acid in the course of extraction from nitric acid solutions with tributyl phosphate in diluent in the presence of uranyl nitrate at various temperatures and its mathematical description

Radiation resistance of hydrocarbon diluents of tributyl phosphate in a two-phase system and carbonate regeneration of the solvent

Influence of temperature on the extraction of actinides from nitric acid solutions into 30% TBP: Description within the framework of a new model

Hydrometallurgical Reprocessing of BREST-OD-300 Mixed Uranium-plutonium Nuclear Fuel

Ways of technetium and neptunium localization in extraction reprocessing of spent nuclear fuel from nuclear power plants

Mathematical description of the extraction of impurity acids with tributyl phosphate in diluent and of the coextraction of the acid anions with uranyl nitrate

Liquid-vapor distribution of acids in HNO3-H2O and HNO3-H2O-HA systems in evaporators

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