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

Published online by Cambridge University Press:  16 February 2017

Michael I. Ojovan  and
Anthony J. Wickham
Michael I. Ojovan*
Affiliation:
Waste Technology Section, Division of Nuclear Fuel Cycle and Waste Technology, Department of Nuclear Energy, International Atomic Energy Agency, PO Box 100, Wagramerstraße 5, Vienna, A-1400Austria
Anthony J. Wickham
Affiliation:
Nuclear Technology Consultancy, Cwmchwefru, Llanafanfawr, Builth Wells, LD2 3PW, UK, and School of Mechanical, Aerospace and Civil Engineering, The University of Manchester, Manchester M13 9PL, UKconfer@globalnet.co.uk
*
*(Email: m.ojovan@iaea.org)
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Abstract

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).

Keywords

radiation effectnuclear materialswaste management
Type
Articles
Information
MRS Advances , Volume 1 , Issue 62: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4117 - 4122
Copyright
Copyright © Materials Research Society 2017 

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References

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