Description
Graphite has been used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium-production reactors, in quantities ranging from a few kilograms to more than 3,000 tonnes, depending on the design. Many of the older reactors have now been shut down, with more approaching the end of their operating lives, and radioactive irradiated graphite have now accumulated worldwide. This publication provides a comprehensive overview of managing irradiated graphite waste provided by the members of The International Project on Irradiated Graphite Processing Approaches (GRAPA) network. This publication is intended for representatives of Member States with a programme involving the management of irradiated graphite, as well as non-governmental or international organizations that represent such programmes regionally or worldwide.
More Information on reusing IAEA copyright material.
Keywords
Managing, Irradiated Graphite Waste, Coordinated Research Project, CRP, Moderator, Reflector of Neutrons, Plutonium-Production Reactors, Design, Radioactive Irradiated Graphite, Member States, International Project on Irradiated Graphite Processing Approaches, GRAPA, Networks, Radioactive Waste Disposal, Radioactive Waste, Management, Waste Disposal, Waste Minimization Management, Liquid Waste Minimization Strategies, Wet Solid Waste Minimization Strategies, Dry Solid Waste, Metal Composition on Waste Arisings, Methodology, Benchmark Waste Minimization Programs, International Case Studies, Specific Aspects, Nuclear Waste Minimization, Publication Review, Impurity Distribution, Models of Reactor Graphite Activation, Radiological Characterization, Leaching Information, Mechanical Characterization, Bulk Characterization, Ageing Management, Inspection, Graphite Retrieval, Dismantling Graphite Core, Treatment, Packaging, Storage
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