ROMAN I. KAN

Engineer, “Pilot & Demonstration Center for Decommissioning of Uranium-Graphite Nuclear Reactors”, JSC (Building 179, 13 Avtodoroga, Seversk, Tomsk Region, 636000, Russia), e-mail: kri@dnrc.ru.

• On the Challenge Associated with the Final Stage of Irradiated Graphite Management from Water-Graphite NPP Reactor Units (2021, №15, p. 10-20)
• Approaches to the Characterization of Graphite UGR Blocks Based on Beta-Emitting С-14 and Сl-36 Radionuclides. Testing at RBMK-1000-type Reactors (2021, №15, p. 21-32)
• Approaches to Graphite Block Characterization by Gamma Radionuclides and their Packaging During UGR Stack Dismantlement (2021, №16, p. 30-43)
• Radiation Situation and its Evaluation while Making an Opening in the Upper Structures of a Shutdown Uranium‑Graphite Reactor (2022, №18, p. 43-56)
• The Dynamics of 14С and 36Сl Radionuclide Leaching from Irradiated RBMK-1000 Graphite in Aqueous Media and its Analysis (2022, №19, p. 35-48)
• Methodological Approaches to the Survey of Storage Facilities for the Radioactive Waste from Uranium-Graphite Reactors (2023, №22, p. 77-90)
• Graphite Removal from Uranium-Graphite Reactors: International Experience and Approaches (2023, №23, p. 41-55)
• Overview of Russian Experience and Approaches Providing Graphite Removal from Uranium-Graphite Reactors (2023, №25, p. 35-54)