In early August, a technical meeting on technologies for processing irradiated graphite waste took place in Vienna, Austria. The Chornobyl NPP was represented by Oleksandr Novikov, Projects and Programs Manager of the Engineering Center.
During the meeting, Oleksandr Novikov presented information on the management of irradiated graphite in Ukraine and shared the experience of the Chornobyl NPP in this area.
The discussion of this issue is of paramount importance, - noted Oleksandr Novikov. – The current situation in the global nuclear energy sector is such that many older reactors have already been shut down, and even more are nearing the end of their operational lives. Worldwide, approximately 250,000 tons of radioactive graphite (irradiated graphite, or 'i-graphite') have accumulated.
In Ukraine alone, the amount of irradiated graphite totals 5.7 thousand tons. Despite progress in developing disposal solutions, increasing amounts of i-graphite remain in temporary storage, awaiting their final destination. In IAEA member states where government policies anticipate the imminent dismantling of reactors, there is a growing recognition of the urgent need to address the challenges associated with graphite management – right up to the industrial implementation of processing technologies and the safe disposal of this material, as well as finding appropriate solutions.
Since no single country, nor the IAEA as a whole, can offer a universal algorithm for handling irradiated graphite, each national nuclear industry is following its own path. This is why the exchange of experience is immensely valuable, as it stimulates the development of new solutions that could eventually form the basis for a global resolution of the i-graphite problem.
We proposed to the IAEA the implementation of an international pilot project for the development of irradiated graphite management technology at the Chornobyl NPP site. However, due to the ongoing combat actions in Ukraine, the risks are currently too high, and this issue can only be considered theoretically for now. Nevertheless, some Western experts have expressed their willingness to provide methodological support to help us initiate this work on-site.
FYI:
Graphite is used as a neutron moderator and reflector at more than 100 nuclear power plants, as well as in many research reactors and plutonium production reactors, in quantities ranging from a few kilograms to over 3,000 tons, depending on the design. The renewed interest in high-temperature reactor concepts in some EU member states has made it essential to emphasise that all carbon materials must be properly managed throughout their lifecycle.