Abstract

The article overviews the existing experience in graphite removal from the stacks of Russian production, power and research uranium-graphite reactors (PUGR, RBMK, AMB, RFT, etc.). It considers the key challenges and some particular features associated with graphite stack dismantlement including the differences in reactor designs, degradation of graphite stacks due to long-term operation, etc. It presents some design solutions and approaches developed to extend the uranium-graphite reactor operation, as well as the experience in the fine-tuning of the graphite stack dismantlement methods.

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