Vol. 65, No. 2, 2023

Radiochemistry

X Russian Conference with International Participation “Radiochemistry-2022” (St. Petersburg, September 26–30, 2022)

Development and Tasks of Radiochemical Technologies: History and Modern Challenges

D. N. Kolupaev, and G. A. Apalkov p. 132 abstract

Radioecological Problems of the Arctic Zone of the Russian Federation: Reasons for Origin, Current status, Prospects

S. V. Antipov, and I. G. Tananaev p. 141 abstract

Fluorine-18 or Gallium-68: The Perspective of PET Radiochemist

R. N. Krasikova p. 158 abstract

Voloxidation of Mixed Nitride Uranium–Plutonium Spent Nuclear Fuel

V. N. Momotov, A. O. Makarov, A. Yu. Volkov, P. V. Lakeev, D. E. Tikhonova, and K. N. Dvoeglazov p. 177 abstract

Tritium Thermal Activation Method. Features of Application, Modern Achievements, and Further Development Prospects

G. A. Badun, and M. G. Chernysheva p. 185 abstract

Preparation of ¹⁷⁷Lu Using Vacuum Sublimation Technology

I. E. Alekseev, and S. A. Krotov p. 198 abstract

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

A. A. Naumov, N. D. Goletskii, E. A. Puzikov, M. V. Mamchich, A. S. Kudinov, and P. I. Soroka p. 205 abstract

Recovery of Americium from Actinide-Lanthanide Fraction of High-Level Waste during Its Transfer to the Oxidation State Am(V)

P. A. Osin, T. I. Trofimov, K. S. Pilyushenko, Yu. M. Kulyako, S. E. Vinokurov, and B. F. Myasoedov p. 213 abstract

Extraction of Yttrium from Carbonate Media Using Mixtures of Aromatic Dihydroxy Compounds and Methyltrioctylammonium Carbonate

A. H. A. Harb, I. V. Balantsev, M. D. Karavan, I. V. Smirnov, and T. S. Aleksandrov p. 219 abstract

Kinetics of the Extraction of Long-Lived Fission Products Present in Spent Nuclear Fuel: a Study by Attenuated Total Reflection IR Spectroscopy

T. S. Aleksandrov, V. V. Timoshenko, A. A. Brechalov, and I. V. Smirnov p. 226 abstract

Separation of Rare Earth and Transplutonium Elements in Carbonate Media

I. V. Balanstev, M. D. Karavan, and I. V. Smirnov p. 230 abstract

Potentiometric Method for Determining the Selectivity of Extraction Systems

A. A. Brechalov, V. V. Timoshenko, T. N. Zakharov, Yu. E. Ermolenko, and E. S. Babitova p. 234 abstract

Rapid Method for Studying the Extraction of Simulated HLW Components by Inductively Coupled Plasma Mass Spectrometry

V. V. Timoshenko, I. V. Smirnov, A. A. Brechalov, and Yu. E. Ermolenko p. 237 abstract

Process Control in Spent Nuclear Fuel Reprocessing Using Multisensor Potentiometry

Yu. S. Savosina, and M. S. Agafonova-Moroz p. 241 abstract

Separation of Boron Isotopes in Extraction Systems Tetrafluoroboric Acid–Organophosphorus Compounds

T. V. Maltseva, E. S. Babitova, and I. V. Smirnov p. 245 abstract

A Precision Spectrophotometric Method for Determining the Mass Fraction of Nuclear Materials

M. A. Shvindin, D. L. Myalochkin, and V. V. Sbitneva p. 249 abstract

Oxidative Dissolution of Triuranium Octoxide in Alkaline Media

N. M. Chervyakov, A. V. Boyarintsev, and S. I. Stepanov p. 253 abstract

Oxidative Dissolution of Uranium Dioxide and Triuranium Octoxide in Carbonate Media

N. M. Chervyakov, A. V. Boyarintsev, and S. I. Stepanov p. 257 abstract

Solvent Extraction Separation of Uranium, Plutonium, and Fission Products in Carbonate Media with Methyltrioctylammonium Carbonate

A. V. Boyarintsev, G. V. Kostikova, S. O. Frankiv, and S. I. Stepanov p. 261 abstract