Processing of Irradiated Graphite: The Outcomes of an IAEA Coordinated Research Project

Dismantling of old reactors and the management of radioactive graphite wastes are becoming increasingly important issues for a number of IAEA Member States. Exchange of information and research cooperation in resolving identical problems between different institutions contributes towards improving waste-management practices, their efficiency, and general safety. The IAEA Coordinated Research Project (CRP) under the title ’Treatment of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal’ was conducted during 2010-2014 and has involved 24 organisations from ten Member States [1]. The CRP has explored both innovative and conventional methods for graphite characterisation, retrieval, treatment, and conditioning technologies and produced an IAEA technical document [2] which has identified a number of unresolved scientific and technical issues such as the need to: 1. Improve the scientific understanding required on creation, chemical form, location and release behaviour (transport models) of radionuclides; 2. Improve predictive models of radioisotope behaviour; 3. Ensure that sampling programmes are statistically representative of the totality of the graphite to be disposed of; 4. Establish an accurate radionuclide inventory; 5. Consider novel alternative dismantling and treatment strategies. The CRP promoted the exchange of technical information on R & D activities and will facilitate practical application for treatment and conditioning of graphite waste. The collaboration continues under the IAEA International Decommissioning and Predisposal Networks (IDN and IPN).