Hostname: page-component-586b7cd67f-l7hp2 Total loading time: 0 Render date: 2024-11-26T18:15:30.742Z Has data issue: false hasContentIssue false
  • English
  • Français

Treatment of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal: Problem and Solutions

Published online by Cambridge University Press:  30 June 2014

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-1400 Austria
Anthony J. Wickham
Affiliation:
Nuclear Technology Consultancy, PO Box 50, Builth Wells, LD2 3XA, UK, and School of Mechanical, Aerospace and Civil engineering, The University of Manchester, Manchester M13 9PL, UK
Get access

Abstract

An overview is given of an International Atomic Energy Agency Coordinated Research Project (CRP) on the treatment of irradiated graphite (i-graphite) to meet acceptance criteria for waste disposal. Graphite is a unique radioactive waste stream, with some quarter-million metric tons worldwide eventually needing to be disposed of. The CRP has involved 24 organizations from 10 Member States. Innovative and conventional methods for i-graphite characterization, retrieval, treatment and conditioning technologies have been explored in the course of this work, and offer a range of options for competent authorities in individual Member States to deploy according to local requirements and regulatory conditions.

Keywords

Cwaste managementradiation effects
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1665: Symposium NW – Scientific Basis for Nuclear Waste Management XXXVII , 2014 , pp. 3 - 12
Copyright
Copyright © Materials Research Society 2014 

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

IAEA, Graphite Moderator Lifecycle Behaviour, Proceedings of a Specialists Meeting held in Bath, United Kingdom, 24–27 Sept 1995; IAEA-TECDOC-901, Vienna (1996).Google Scholar
IAEA, 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).Google Scholar
IAEA (2010). Progress in Radioactive Graphite Waste Management. IAEA-TECDOC-1647, IAEA, Vienna (2010).Google Scholar
IAEA, Characterization, Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors. IAEA-TECDOC-1521, IAEA, Vienna (2006).Google Scholar
White, I.F., Smith, G.M., Saunders, L.J., Kaye, C.J., Martin, T.J., Clarke, G.H. and Wakerley, M.W., Assessment of Management Modes for Graphite from Reactor Decommissioning, Commission of the European Communities, EUR 9232, Brussels, (1984).Google Scholar
Banford, A., Eccles, H., Graves, M., von Lensa, W., Norris, S.. CARBOWASTE – An Integrated Approach to Irradiated Graphite. Nuclear Future, 4, 268–270 (2008).Google Scholar
IAEA. (2013). Nuclear Technology Review. IAEA, Vienna, 170 p. (2013).Google Scholar
Rublevskiy, V.P.. Commercial nuclear reactors and 14C. Atomic Energy, 113, 143–147 (2012).CrossRefGoogle Scholar
IAEA IMMONET SharePoint Site. http://nucleus.iaea.org/sites/nefw-projects/IMMONET/SitePages/Home.aspx (2013).Google Scholar
IAEA Irradiated Graphite Treatment CRP Site. http://nucleus.iaea.org/sites/nefw-projects/IMMONET/graphite-crp/SitePages/Home.aspx (2013).Google Scholar
Poncet, B., Petit, L.. Method to assess the radionuclide inventory of irradiated graphite waste from gas-cooled reactors. J. Radioanal. Nucl. Chem., 296, 3, 15 p., DOI: 10.1007/s10967-013-2519-6 (2013).Google Scholar
Guiroy, J.-J., Graphite Waste Incineration in a Fluidised Bed, in Ref [1] above, 193–203 (1996).Google Scholar
Karlina, O., Ojovan, M., Pavlova, G., Klimov, V.. Thermodynamic modelling and experimental tests of irradiated graphite molten salt decontamination. Mater. Res. Soc. Symp. Proc. 1518, 6 p., DOI: http://dx.doi.org/10.1557/opl.2013.72 (2013).CrossRefGoogle Scholar
Autorité de Sûreté Nucléaire, Ministère de l’Écologie du Développement durable et de l’Énergie, Plan Nacional de Gestion des Matières et des Déchets Radioactifs 2013 – 2015, Paris, April 2013.Google Scholar