Updating irradiated graphite disposal: Project 'GRAPA' and the international decommissioning network.
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.
Nuclear Graphite Consultancy, Builth Wells, and the School of Mechanical, Aerospace and Civil Engineering, The University of Manchester, UK. Electronic address: tony@tonywickham.co.uk.
Anthony
A
Wickham
University of Applied Sciences of Aachen, Germany.
Hans-Jürgen
HJ
Steinmetz
International Atomic Energy Agency, Vienna, Austria.
Patrick
P
O'Sullivan
International Atomic Energy Agency, Vienna, Austria.
Michael I
MI
Ojovan
D006108:Graphite / Q000737:chemistry*; D011835:Radiation Protection; D011850:Radioactive Waste / Q000032:analysis*; D018505:Waste Management / Q000379:methods*
D011850:Radioactive Waste; D006108:Graphite
Decommissioning; Graphite; Radioactive waste