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Application of Unified Model with TBP Dilution to Description of Extraction of Nitrates of Tetravalent Zirconium and Hafnium Actinides from Nitrate Solutions

Radiochemistry (New York, N.Y.), 2020-04, Vol.62 (4), p.492-498

2020

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Use of a Unified Model with TBP Dilution for Describing the Extraction of Nitric Acid and Hexavalent Actinide Nitrates in Multicomponent Nitrate Systems

Radiochemistry (New York, N.Y.), 2019-09, Vol.61 (5), p.554-561

2019

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Approaches to a Mathematical Modeling of the Density of Nitrate Solutions on the Basis of Concepts of Apparent Molar Volume As Applied to Hydrometallurgical Processes of the Nuclear Fuel Cycle

Radiochemistry (New York, N.Y.), 2020, Vol.62 (1), p.22-30

2020

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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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Influence of temperature on Pu(IV) extraction from nitric acid solutions into 30% TBP, considered within the framework of A.M. Rozen’s model and of a new (multireaction) model

Radiochemistry (New York, N.Y.), 2017-07, Vol.59 (4), p.351-353

2017

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Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model

Radiochemistry (New York, N.Y.), 2017-03, Vol.59 (2), p.143-151

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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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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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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A new approach to mathematical description of the extraction of HNO3, U(VI), and other hexavalent actinides with tributyl phosphate in a mixture with paraffins

Radiochemistry (New York, N.Y.), 2013-05, Vol.55 (3), p.291-297

2013

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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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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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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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Dissolution of WWER-1000 spent nuclear fuel in a weakly acidic solution of iron nitrate and recovery of actinides and rare earth elements with TBP solutions

Radiochemistry (New York, N.Y.), 2016-05, Vol.58 (3), p.265-270

2016

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New data on joint extraction of actinide nitrates and some acids with tributyl phosphate diluted with paraffins and mathematical description of the process by A.M. Rozen’s Model

Radiochemistry (New York, N.Y.), 2013-03, Vol.55 (2), p.190-202

2013

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Extraction of tetravalent actinides and zirconium from nitric acid solutions with tributyl phosphate in diluent in the presence of uranyl nitrate and its mathematical description within the framework of the new approach

Radiochemistry (New York, N.Y.), 2013-09, Vol.55 (5), p.481-485

2013

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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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Extraction of nitric acid and uranyl nitrate with tributyl phosphate in diluent in the presence of salting-out agents and its mathematical description

Radiochemistry (New York, N.Y.), 2013-07, Vol.55 (4), p.369-376

2013

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Development and trials of a process for extraction recovery of 99Mo for medical purposes from dissolved irradiated uranium targets

Radiochemistry (New York, N.Y.), 2015-05, Vol.57 (3), p.292-306

2015

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Extraction of zirconium with tributyl phosphate from nitric acid solutions

Radiochemistry (New York, N.Y.), 2008-06, Vol.50 (3), p.256-260

2008

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Extraction of molybdenum from supersaturated solutions in nitric acid with tributyl phosphate solutions

Radiochemistry (New York, N.Y.), 2010-04, Vol.52 (2), p.180-188

2010

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Extraction of Mo from solutions in HNO3 and other mineral acids with solutions of dibutyl hydrogen phosphate in a diluent

Radiochemistry (New York, N.Y.), 2010-08, Vol.52 (4), p.408-417

2010

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Interaction of HDBP with Zr in extraction

Radiochemistry (New York, N.Y.), 2009-04, Vol.51 (2), p.149-155

2009

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Distribution of HDBP in two-phase systems consisting of aqueous nitric acid, organic diluent (with or without TBP), and HDBP or its zirconium salt

Radiochemistry (New York, N.Y.), 2007-08, Vol.49 (4), p.391-396

2007

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Application of Unified Model with TBP Dilution to Description of Extraction of Nitrates of Tetravalent Zirconium and Hafnium Actinides from Nitrate Solutions

Use of a Unified Model with TBP Dilution for Describing the Extraction of Nitric Acid and Hexavalent Actinide Nitrates in Multicomponent Nitrate Systems

Approaches to a Mathematical Modeling of the Density of Nitrate Solutions on the Basis of Concepts of Apparent Molar Volume As Applied to Hydrometallurgical Processes of the Nuclear Fuel Cycle

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

Influence of temperature on Pu(IV) extraction from nitric acid solutions into 30% TBP, considered within the framework of A.M. Rozen’s model and of a new (multireaction) model

Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model

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

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

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

A new approach to mathematical description of the extraction of HNO3, U(VI), and other hexavalent actinides with tributyl phosphate in a mixture with paraffins

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

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

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

Dissolution of WWER-1000 spent nuclear fuel in a weakly acidic solution of iron nitrate and recovery of actinides and rare earth elements with TBP solutions

New data on joint extraction of actinide nitrates and some acids with tributyl phosphate diluted with paraffins and mathematical description of the process by A.M. Rozen’s Model

Extraction of tetravalent actinides and zirconium from nitric acid solutions with tributyl phosphate in diluent in the presence of uranyl nitrate and its mathematical description within the framework of the new approach

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

Extraction of nitric acid and uranyl nitrate with tributyl phosphate in diluent in the presence of salting-out agents and its mathematical description

Development and trials of a process for extraction recovery of 99Mo for medical purposes from dissolved irradiated uranium targets

Extraction of zirconium with tributyl phosphate from nitric acid solutions

Extraction of molybdenum from supersaturated solutions in nitric acid with tributyl phosphate solutions

Extraction of Mo from solutions in HNO3 and other mineral acids with solutions of dibutyl hydrogen phosphate in a diluent

Interaction of HDBP with Zr in extraction

Distribution of HDBP in two-phase systems consisting of aqueous nitric acid, organic diluent (with or without TBP), and HDBP or its zirconium salt

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