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Comparison of Dynamic Tests of the Modified Purex Process Flowsheet Using 30 and 45% TBF in Isoparaffin

Radiochemistry (New York, N.Y.), 2024-02, Vol.66 (1), p.35-43

2024

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Substantiation of the Practical Feasibility of the Modified Scheme of Purex Process with an Increased TBP Concentration Using Mathematical Modeling

Radiochemistry (New York, N.Y.), 2023-04, Vol.65 (2), p.205-212

2023

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Description of the Extraction of Trivalent REE and TPE Nitrates with Tributyl Phosphate and Its Solutions in Paraffins in the Presence of Nitric Acid and Salting-out Agents Using a Unified Model

Radiochemistry (New York, N.Y.), 2019-11, Vol.61 (6), p.689-693

2019

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Description of the Extraction of Rare Earth Element Nitrates from Weakly Acidic Solutions with Concentrated Tributyl Phosphate Solutions

Radiochemistry (New York, N.Y.), 2019-07, Vol.61 (4), p.447-458

2019

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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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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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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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Status of and Prospects for Using Carbide Fuel

Atomic energy (New York, N.Y.), 2015-04, Vol.117 (6), p.388-393

2015

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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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Possibilities of concentrating 99Мо by extraction with solutions of aliphatic hydroxamic acids in alcohols

Radiochemistry (New York, N.Y.), 2016, Vol.58 (4), p.394-404

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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Salt-Free Reprocessing of Spent Carbide Fuel for the Example of AM-Reactor Fuel

Atomic energy (New York, N.Y.), 2015-04, Vol.117 (6), p.394-408

2015

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Features of Canada’s Sanctions Legislation and Trends in Sanctions Appeal Jurisprudence

Kontury globalʹnykh transformat͡s︡iĭ : politika, ėkonomika, pravo, 2024-08, Vol.17 (1), p.105-121

2024

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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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Obosnovanie prakticheskoy realizuemosti skhemy modifitsirovannogo Pureks-protsessa s povyshennoy kontsentratsiey TBF s ispol'zovaniem matematicheskogo modelirovaniya

Радиохимия, 2023-04, Vol.65 (2), p.179-187

2023

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The Effective Convectivity Model for Simulation of Molten Metal Layer Heat Transfer in a Boiling Water Reactor Lower Head

Science and Technology of Nuclear Installations, 2013-01, Vol.2013 (2013), p.1-14

2013

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Особенности санкционного регулирования в США, ЕС и Великобритании: сравнительный анализ

Polis (Moscow, Russia), 2022-01 (6), p.151

2022

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TPE and RE Extraction during Long-lived Radionuclide Partitioning in Combination with PUREX-process Using a Single TBP-Based Solvent

Solvent extraction and ion exchange, 2019-09, Vol.37 (6), p.435-445

2019

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Analysis of ligand, binding to kringles 4 and 5 fragments from human plasminogen

Thrombosis research, 1989-02, Vol.53 (3), p.243-252

1989

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Service systems of small spacecrafts

AIP Conference Proceedings, 2021, Vol.2318 (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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COMPARATIVE ANALYSIS OF THE MODIFIED MRAC-MIT SYSTEM AND MRAC-LYAPUNOV SYSTEM

Informatika i sistemy upravleniya, 2021 (1), p.31-43

2021

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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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Comparison of Dynamic Tests of the Modified Purex Process Flowsheet Using 30 and 45% TBF in Isoparaffin

Substantiation of the Practical Feasibility of the Modified Scheme of Purex Process with an Increased TBP Concentration Using Mathematical Modeling

Description of the Extraction of Trivalent REE and TPE Nitrates with Tributyl Phosphate and Its Solutions in Paraffins in the Presence of Nitric Acid and Salting-out Agents Using a Unified Model

Description of the Extraction of Rare Earth Element Nitrates from Weakly Acidic Solutions with Concentrated Tributyl Phosphate Solutions

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

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

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

Status of and Prospects for Using Carbide Fuel

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

Possibilities of concentrating 99Мо by extraction with solutions of aliphatic hydroxamic acids in alcohols

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

Salt-Free Reprocessing of Spent Carbide Fuel for the Example of AM-Reactor Fuel

Features of Canada’s Sanctions Legislation and Trends in Sanctions Appeal Jurisprudence

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

Obosnovanie prakticheskoy realizuemosti skhemy modifitsirovannogo Pureks-protsessa s povyshennoy kontsentratsiey TBF s ispol'zovaniem matematicheskogo modelirovaniya

The Effective Convectivity Model for Simulation of Molten Metal Layer Heat Transfer in a Boiling Water Reactor Lower Head

Особенности санкционного регулирования в США, ЕС и Великобритании: сравнительный анализ

TPE and RE Extraction during Long-lived Radionuclide Partitioning in Combination with PUREX-process Using a Single TBP-Based Solvent

Analysis of ligand, binding to kringles 4 and 5 fragments from human plasminogen

Service systems of small spacecrafts

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

COMPARATIVE ANALYSIS OF THE MODIFIED MRAC-MIT SYSTEM AND MRAC-LYAPUNOV SYSTEM

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

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