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Updated: Mar 7, 2026

Irradiator Commissioning and Dosimetry for Assessment of LQ α and β Parameters, Radiation Dosing Schema, and in vivo Dose Deposition
Published on: March 11, 2021
Updating irradiated graphite disposal: Project 'GRAPA' and the international decommissioning network
Anthony Wickham1, Hans-Jürgen Steinmetz2, Patrick O'Sullivan3
1Nuclear Graphite Consultancy, Builth Wells, and the School of Mechanical, Aerospace and Civil Engineering, The University of Manchester, UK.
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.
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