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Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal

Results of a Coordinated Research Project

IAEA TECDOC No. 1790
English IAEA-TECDOC-1790 978-92-0-104016-9
148 26 18.00 2016

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Description

Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants.

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Keywords

Waste Management, Radioactive Waste Disposal, Hazardous Wastes, Nuclear Power Plants, Research Reactors, Irradiated Graphite, Regulations, Countries, Vitreous Immobilization, Cementation, Processing and Treatment, Storage Facilities, CRP, Coordinated Research Project, Recommendations, Graphite Management Issues, National Strategy, Waste Acceptance Criteria, Radioisotopes, Leaching

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