International Conference on the Safety of Radioactive Waste Management, Decommissioning, Environmental Protection and Remediation: Ensuring Safety and Enabling Sustainability

Determining the optimal strategy of disposing irradiated graphite moderator

Not scheduled

20m

M-Building (IAEA Headquarters, Vienna)

POSTER Track 5 - Practical experiences in integrating safety and sustainable development

Speakers

Ivan Stepanov Nikita Sidorov (National Research Nuclear University MEPhI)

Description

This paper discusses ways to manage irradiated graphite during the decommissioning of uranium-graphite reactors. Examples are given of the application of different strategies and methods of reactor graphite treatment at different reactors.
The concept of a shipping container is proposed. Thermo-mechanical and neutron-physical calculations are given.

Presentation materials

MAGATE statya.pdf