Yu. S. Fedorov

ORCID: 0000-0001-8510-8915
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About
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Research Areas
  • Radioactive element chemistry and processing
  • Extraction and Separation Processes
  • Chemical Synthesis and Characterization
  • Nuclear Materials and Properties
  • Graphite, nuclear technology, radiation studies
  • Nuclear reactor physics and engineering
  • Molten salt chemistry and electrochemical processes
  • Metal Extraction and Bioleaching
  • Field-Flow Fractionation Techniques
  • Inorganic Fluorides and Related Compounds
  • Radioactive contamination and transfer
  • Fiber-reinforced polymer composites
  • Nuclear and radioactivity studies
  • Material Properties and Applications
  • Inorganic and Organometallic Chemistry
  • Advanced Power Generation Technologies
  • Analytical chemistry methods development
  • Nuclear materials and radiation effects
  • Boron Compounds in Chemistry
  • Minerals Flotation and Separation Techniques
  • Adsorption, diffusion, and thermodynamic properties of materials
  • Fusion materials and technologies
  • Industrial Engineering and Technologies
  • Radiopharmaceutical Chemistry and Applications
  • Recycling and Waste Management Techniques

St. Petersburg State Technological Institute
2017-2024

V. G. Khlopin Radium Institute
2007-2020

Bauman Moscow State Technical University
2020

Kurchatov Institute
2019

Research Institute of Scientific Research and Production Association
2013

A new approach to simulation of interphase equilibrium at extraction actinides in various valent states, some fission products, and admixed acids from nitric acid media the presence salting out agents by diluted TBP has been developed. It is based on a set simultaneous chemical reactions, including salvation, hydrolysis, complexing, etc., characterized apparent concentration constants. software package was created for spent fuel component distribution multistage countercurrent processes.

10.1080/07366299.2014.993238 article EN Solvent Extraction and Ion Exchange 2014-12-03

The careful control of actinide distribution between 30% tributylphosphate (TBP) in organic diluent and nitric acid is vital to the successful operation nuclear fuel reprocessing plants. Uranium (VI) tetravalent actinides are extracted into phase as nitrate complexes UO 2 (NO 3 ) An(NO 4 respectively. presence dibutylphosphate (HDBP), a decomposition product, affects this due formation strong, soluble, phosphate ions. This paper describes investigation U(VI), U(IV), Np(IV) Pu(IV)...

10.1524/ract.2000.88.5.283 article EN Radiochimica Acta 2000-05-01

ABSTRACT The influence of di-n-butyl phosphoric acid (HDBP) upon extraction uranium(VI) by tri-n-butyl phosphate (TBP) from 0·5–3·0 M nitric solutions has been studied. It shown that the distribution coefficient D u for 1·1 TBP in tri-decane or xylene is increased when HDBP present organic phase. For iso-molar (TBP + HDBP) with a total concentration 0·36 M, and Uranium(VI) aqueous up to 10–20 g/1, maximum value Du observed TBP/HDBP =1; higher U(VI) gradually disappears, growing monotonically...

10.1080/07366299908934611 article EN Solvent Extraction and Ion Exchange 1999-03-01
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