OV Shmidt

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Publications in SciGraph latest 50 shown

  • 2018-12 Modeling of crystallization process for SNF reprocessing in JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • 2018-09 Optimization and Diagnostics Code for Technological Processes: Radiochemical Production Simulator in ATOMIC ENERGY
  • 2018-07 Development of a Mathematical Model for Denitration of Actinide Nitrates under the Action of UHF Radiation in RADIOCHEMISTRY
  • 2018-05 A Model for Calculating the Characteristics of Separation of Transplutonium and Rare Earth Elements by High-Performance Liquid Chromatography in RADIOCHEMISTRY
  • 2018-05 Kinetics of Thermal Degradation of VP-1AP Anion-Exchange Resin in the Nitrate Form in RADIOCHEMISTRY
  • 2017-11 Beyond-design-basis regimes of uranium stripping and of carbonate regeneration of the solvent in RADIOCHEMISTRY
  • 2017-09 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 in RADIOCHEMISTRY
  • 2017-06 Vizart Software for Balance Calculations of Material Flows in Closed Nuclear Fuel Cycle Technologies in ATOMIC ENERGY
  • 2016-10 Next Generation Design Codes for a New Technological Platform for Nuclear Power in ATOMIC ENERGY
  • 2016-07 Simulation of closed nuclear fuel cycle processes as a tool for the development and optimization of radiochemical technologies in RADIOCHEMISTRY
  • 2016-07 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 in RADIOCHEMISTRY
  • 2016-05 РH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor in RADIOCHEMISTRY
  • 2015-03 Influence of temperature on the extraction of actinides from nitric acid solutions into 30% TBP: Description within the framework of a new model in RADIOCHEMISTRY
  • 2013-12 Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant in ATOMIC ENERGY
  • 2010-10 A crystal-chemical approach in the development of phosphate materials as environmentally safe chemical forms of utilization of spent Cs-containing ferrocyanide sorbents in RADIOCHEMISTRY
  • 2010-08 Silicates of leucite structure as environmentally safe forms of cesium and strontium immobilization in RADIOCHEMISTRY
  • 2010-02 Precipitation of 137Cs with microorganisms from aqueous industrial process solutions in RADIOCHEMISTRY
  • 2009-08 Precipitation of cesium jointly with uranium from nitric acid liquid radioactive wastes to obtain solid matrices for long-term storage in RADIOCHEMISTRY
  • 2009-08 Extraction of Eu and Am with extractants based on carbamoyl phosphine oxide (CMPO) in RADIOCHEMISTRY
  • 2009-04 Interaction of HDBP with Zr in extraction in RADIOCHEMISTRY
  • 2009-01 Dibutyl phosphoric acid and its acid zirconium salt as an extractant for the separation of transplutonium elements and rare earths and for their partitioning in JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • 2007-12 Combined processing scheme of WWER-1000 spent nuclear fuel: 2. Experimental trial of extraction processing of fluoride cinder in RADIOCHEMISTRY
  • 2007-08 Distribution of HDBP in two-phase systems consisting of aqueous nitric acid, organic diluent (with or without TBP), and HDBP or its zirconium salt in RADIOCHEMISTRY
  • 2007-06 Extraction of alkaline-earth elements from nitric acid with a solution of HDBP zirconium salt in RADIOCHEMISTRY
  • 2006-05 Extraction of HNO3 with solutions of zirconium salt of dibutyl hydrogen phosphate in 30% tributyl phosphate and in xylene in RADIOCHEMISTRY
  • 2005-07 Radiation Chemical Behavior of Tributyl Phosphate, Dibutylphosphoric Acid, and Its Zirconium Salt in Organic Solutions and Two-Phase Systems in RADIOCHEMISTRY
  • 2004-03 Mathematical Simulation of Steady-State Concentration Profiles in Extraction Cascades for Reprocessing NPP Spent Fuel Using TBP-Compatible Processes (SUPERPUREX) in RADIOCHEMISTRY
  • 2003-11 Effect of TBP on Extraction of REE and TPE from Nitric Acid Solutions with Dibutylphosphoric Acid and Its Zirconium Salt in RADIOCHEMISTRY
  • 2003-11 Methods for Recovering Molybdenum from High-Level Raffinate of Extraction Reprocessing of NPP Spent Fuel in RADIOCHEMISTRY
  • 2003-11 Partitioning of High-Level Waste with an Extractant Based on Chlorinated Cobalt Dicarbollide and Dibutylphosphoric Acid Zirconium Salt in RADIOCHEMISTRY
  • 2003-11 Effect of TBP on Extraction of REE and TPE with 4d Element Salts of Dibutylphosphoric Acid in RADIOCHEMISTRY
  • 2003-01 Extraction of transplutionium and rare-earth elements, molybdenum and iron with zirconium salt of dibutyl phosphoric acid in CZECHOSLOVAK JOURNAL OF PHYSICS
  • 2003-01 TPE/REE separation with the use of zirconium salt of HDBP in CZECHOSLOVAK JOURNAL OF PHYSICS
  • 2002-09 Extraction Properties of Dibutylphosphoric Acid Zirconium Salt in Recovery of Transplutonium and Rare-Earth Elements from Nitric Acid Solution in RADIOCHEMISTRY
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