Siberian Federal University 
- Issue
- Journal of Siberian Federal University. Engineering & Technologies. 2026 19 (4)
- Authors
- Ivshin, Aleksey V.; Kalyutik, Aleksandr A.; Modestov, Victor S.; Shadelko, Filipp V.
- Contact information
- Ivshin, Aleksey V.: Peter the Great St. Petersburg Polytechnic University (St. Petersburg, Russian Federation); ; Kalyutik, Aleksandr A.: Peter the Great St. Petersburg Polytechnic University (St. Petersburg, Russian Federation); Modestov, Victor S. : Peter the Great St. Petersburg Polytechnic University (St. Petersburg, Russian Federation); Shadelko, Filipp V. : Peter the Great St. Petersburg Polytechnic University (St. Petersburg, Russian Federation)
- Keywords
- transport and packaging set; irradiated blocks of graphite moderator; radioactive material; design accident; safety; tightness; numerical modeling; ultimate deformation; residual deformation due to destruction
- Abstract
Ensuring the safe handling of irradiated graphite moderators during the decommissioning of RBMK‑1000 reactor nuclear power units is an important task. To achieve it, a design of a special container intended for the transportation of irradiated graphite moderators from nuclear power plant sites is proposed. The results of numerical simulations of the main accident tests of the container, as specified by the IAEA safety standards, are presented: free fall from a height of 9 meters onto a rigid surface and free fall from a height of 1 meter onto a steel rod. These tests allow for the evaluation of the container’s safety, its ability to withstand impact loads and maintain its structural integrity. The calculations indicate that the proposed container design meets safety requirements and maintains its overall integrity and leak tightness
- Pages
- 504–514
- EDN
- ZEBTZN
- Paper at repository of SibFU
- https://elib.sfu-kras.ru/handle/2311/158569
This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License (CC BY-NC 4.0).