Abstract
The methodological, regulatory and technological aspects of handling radioactive graphite from decommissioned nuclear reactors are discussed. Destructive and decontamination methods of "neutralization" of graphite are considered. An analysis of the feasibility and economic consequences of applying different approaches to the final isolation of graphite waste from industrial and power reactors has been undertaken. Proposals for optimizing the reactor graphite disposal strategy are formulated
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Schedule a callMore From: Bulletin of the Saint Petersburg State Institute of Technology (Technical University)
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