PAVEL A. BLOKHIN

Head of laboratory, Nuclear Safety Institute of the Russian Academy of Sciences (52, Bolshaya Tulskaya st., Moscow, 115191, Russia), е-mail: blokhin@ibrae.ac.ru.

• Opportunities for Controlling Borosilicate Glass Parameters During VVER­‑1000 SNF Reprocessing at PDC MCC (2019, №7, p. 49-57)
• Fifth Scientific and Technical Workshop on Challenges in Radioactive Waste Processing and Conditioning (2022, №20, p. 124-125)
• Sorption Influence on Iodine-129 Release from the DGR’S Near Field (2024, №26, p. 57-68)
• Analysis of the RW Radionuclide Composition in the Context of Long-Term Safety of Its Disposal (2018, №3, p. 44-51)
• Capabilities of TRACT code to resolve the problems of radioactive (2018, №3, p. 95-104)
• Development of an Algorithm for Estimating the Radionuclide Composition of Vitrified HLW of FSUE “PA “Mayak” for the Purpose of Their Safe Disposal (2018, №4, p. 102-110)
• IAEA Spent Fuel Management Conference (2019, №9, p. 116-118)
• Radiation Characteristics of Borosilicate Glass Containing High-Level Waste (2020, №12, p. 93-100)
• TRACT Computer Code Application in the Assessment of SNF and RW Class 1 Radionuclide Compositions and Radiation Characteristics (2020, №13, p. 99-111)
• Radiation resistance of borosilicate glass to beta and gamma radiation evaluated using the accelerated proton method (2021, №14, p. 8-18)
• Refinement of KORIDA Software Complex and Its Application in Addressing SNF and RW Management Problems (2022, №20, p. 107-116)
• Validation of Nuclide Kinetics Code TRACT for the Assessment of SNF and RW Radiation Characteristics (2022, №21, p. 48-57)
• Considerations on the Regulation of Production and Consumption Waste Management During Nuclear Site Cleanup (2024, №28, p. 32-42)