Updating irradiated graphite disposal: Project ‘GRAPA’ and the international decommissioning network

Abstract

Demonstrating competence in planning and executing the disposal of radioactive wastes is a key factor in the public perception of the nuclear power industry and must be demonstrated when making the case for new nuclear build. This work addresses the particular waste stream of irradiated graphite, mostly derived from reactor moderators and amounting to more than 250,000 tonnes world-wide. Use may be made of its unique chemical and physical properties to consider possible processing and disposal options outside the normal simple classifications and repository options for mixed low or intermediate-level wastes. The IAEA has an obvious involvement in radioactive waste disposal and has established a new project ‘GRAPA’ – Irradiated Graphite Processing Approaches – to encourage an international debate and collaborative work aimed at optimising and facilitating the treatment of irradiated graphite.