EA Puzikov


Ontology type: schema:Person     


Person Info

NAME

EA

SURNAME

Puzikov

Publications in SciGraph latest 50 shown

  • 2018-12 Concentrating 99Mo from LEU by extraction with higher hydroxamic acids solutions in alcohols C8–C10 in JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • 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
  • 2017-07 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 in RADIOCHEMISTRY
  • 2017-03 Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model in RADIOCHEMISTRY
  • 2016-09 Mathematical model of precipitation of barium and strontium nitrates from nitric acid solutions and their mutual effect 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 Influence of pressure (temperature) on the nitric acid distribution between the liquid and vapor in the course of evaporation of nitric acid radioactive waste in RADIOCHEMISTRY
  • 2016-03 Effect of salting-out agents on nitric acid distribution between liquid and vapor in the course of evaporation of nitric acid radioactive waste in RADIOCHEMISTRY
  • 2015-09 Coprecipitation of barium and strontium nitrates in the course of crystallization from nitric acid solutions and simulated high-level PUREX process raffinate in RADIOCHEMISTRY
  • 2015-05 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 in RADIOCHEMISTRY
  • 2015-04 Nitric acid adduct formation during crystallization of barium and strontium nitrates and their co-precipitation from nitric acid media in JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • 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
  • 2015-01 Extraction of molybdenum from nitric acid solutions with tributyl phosphate in RADIOCHEMISTRY
  • 2014-11 Preliminary studies of dynamic regimes in the extraction-scrubbing groups of units of the experimental and demonstration center (EDC) using mathematical modeling in RADIOCHEMISTRY
  • 2014-09 Ways of technetium and neptunium localization in extraction reprocessing of spent nuclear fuel from nuclear power plants in RADIOCHEMISTRY
  • 2014-05 Composition of precipitates of barium and strontium nitrates crystallizing from nitric acid solutions in RADIOCHEMISTRY
  • 2014-03 Mathematical description of the extraction of impurity acids with tributyl phosphate in diluent and of the coextraction of the acid anions with uranyl nitrate in RADIOCHEMISTRY
  • 2013-09 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 in RADIOCHEMISTRY
  • 2013-07 Extraction of nitric acid and uranyl nitrate with tributyl phosphate in diluent in the presence of salting-out agents and its mathematical description in RADIOCHEMISTRY
  • 2013-05 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 in RADIOCHEMISTRY
  • 2013-03 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 in RADIOCHEMISTRY
  • 2012-07 Nitric acid purification from admixtures of volatile acids by fractionation during waste evaporation at a spent nuclear fuel reprocessing company in THEORETICAL FOUNDATIONS OF CHEMICAL ENGINEERING
  • 2012-02 Extraction of molybdenum from nitric acid solutions with solutions of dibutyl hydrogen phosphate zirconium salt in RADIOCHEMISTRY
  • 2011-12 A spectroscopic study of molybdenum extracts in organic solutions of dibutyl hydrogen phosphate in equilibrium with aqueous nitric acid solutions in RADIOCHEMISTRY
  • 2011-09 Problems of modernization of spent nuclear fuel extraction processing in RUSSIAN JOURNAL OF GENERAL CHEMISTRY
  • 2010-08 Extraction of Mo from solutions in HNO3 and other mineral acids with solutions of dibutyl hydrogen phosphate in a diluent in RADIOCHEMISTRY
  • 2010-04 Extraction of molybdenum from supersaturated solutions in nitric acid with tributyl phosphate solutions in RADIOCHEMISTRY
  • 2009-11 Development, analysis, and simulation of a technological structure for reprocessing irradiated nuclear fuel from nuclear power plants by water-extraction methods in ATOMIC ENERGY
  • 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
  • 2007-08 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
  • 2004-03 Mathematical Simulation of Steady-State Concentration Profiles in Extraction Cascades for Reprocessing NPP Spent Fuel Using TBP-Compatible Processes (SUPERPUREX) in RADIOCHEMISTRY
  • 2003-01 Extraction of transplutionium and rare-earth elements, molybdenum and iron with zirconium salt of dibutyl phosphoric acid 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
  • 2001-11 Above-Extreme Extraction Mode in the Purex Process: 1. Calculation of the Pu and U Distribution in the Head Extractor in RADIOCHEMISTRY
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