A Yu Shadrin


Ontology type: schema:Person     


Person Info

NAME

A Yu

SURNAME

Shadrin

Publications in SciGraph latest 50 shown

  • 2018-12 Modeling of crystallization process for SNF reprocessing in JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • 2018-06 Testing of an Integrated Nitrogen Oxide Catcher in ATOMIC ENERGY
  • 2018-02 Local Gas Purification System in Spent Nitride Fuel Oxidation in ATOMIC ENERGY
  • 2017-07 Radiochemical analysis of a sample of mixed uranium–plutonium nitride fuel in RADIOCHEMISTRY
  • 2016-12 Comparison of Closed Nuclear Fuel Cycle Technologies in ATOMIC ENERGY
  • 2016-05 РH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor in RADIOCHEMISTRY
  • 2015-05 Preparation of uranium oxides by reductive denitration of uranyl nitrate under microwave heating in RADIOCHEMISTRY
  • 2014-03 UO2, NpO2 and PuO2 preparation in aqueous nitrate solutions in the presence of hydrazine hydrate in JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • 2013-12 Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant in ATOMIC ENERGY
  • 2013-11 Preparation of Np, Pu, and U dioxides in nitric acid solutions in the presence of hydrazine hydrate in RADIOCHEMISTRY
  • 2013-11 Preparation of uranium oxides in nitric acid solutions by the reaction of uranyl nitrate with hydrazine hydrate in RADIOCHEMISTRY
  • 2013-09 Batching of spent AMB nuclear fuel for reprocessing at the industrial association mayak in ATOMIC ENERGY
  • 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
  • 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
  • 2010-10 Solubility and coprecipitation of barium and strontium nitrates in HNO3 solutions and multicomponent systems in RADIOCHEMISTRY
  • 2010-08 New approaches to reprocessing of oxide nuclear fuel in RADIOCHEMISTRY
  • 2010-04 Formation of molybdenum and zirconium precipitates in concentrated uranyl nitrate 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
  • 2009-08 Extraction of Eu and Am with extractants based on carbamoyl phosphine oxide (CMPO) in RADIOCHEMISTRY
  • 2008-06 Solubility of plutonium nitrate in uranyl nitrate hexahydrate melt in RADIOCHEMISTRY
  • 2006-01 Radiation resistance of a series of organophosphorus extractants in RADIOCHEMISTRY
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