International Atomic Energy Agency, ’Nuclear Graphite Waste Management: Technical Committee Meeting on Nuclear Graphite Waste Management’, Manchester UK, 18–20 October 1999, IAEA CD-ROM 01-00120, Vienna (2001). International Atomic Energy Agency, ’Graphite Moderator Lifecycle Behaviour’, Proceedings of a Specialists Meeting held in Bath, United Kingdom, 24–27 Sept 1995 IAEA-TECDOC-901, Vienna (1996). Results of a Coordinated Research Project’, IAEA-TECDOC- in press, (2016). International Atomic Energy Agency, ’Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Wickham, ’Treatment of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal: Problem and Solutions’, Mat. The collaboration continues under the IAEA International Decommissioning and Predisposal Networks (IDN and IPN). The CRP promoted the exchange of technical information on R & D activities and will facilitate practical application for treatment and conditioning of graphite waste. Improve predictive models of radioisotope behaviour Įnsure that sampling programmes are statistically representative of the totality of the graphite to be disposed of Įstablish an accurate radionuclide inventory Ĭonsider novel alternative dismantling and treatment strategies. Improve the scientific understanding required on creation, chemical form, location and release behaviour (transport models) of radionuclides The CRP has explored both innovative and conventional methods for graphite characterisation, retrieval, treatment, and conditioning technologies and produced an IAEA technical document which has identified a number of unresolved scientific and technical issues such as the need to: 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. Exchange of information and research cooperation in resolving identical problems between different institutions contributes towards improving waste-management practices, their efficiency, and general safety. Dismantling of old reactors and the management of radioactive graphite wastes are becoming increasingly important issues for a number of IAEA Member States.