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An overview of research activities on cementitious materials for radioactive waste management

Published online by Cambridge University Press:  23 March 2012

Zoran Drace ,
Irena Mele ,
Michael I. Ojovan  and
R. O. Abdel Rahman
Zoran Drace
Affiliation:
International Atomic Energy Agency, Wagramer Strasse 5, PO Box 100, 1400 Vienna, Austria
Irena Mele
Affiliation:
International Atomic Energy Agency, Wagramer Strasse 5, PO Box 100, 1400 Vienna, Austria
Michael I. Ojovan
Affiliation:
International Atomic Energy Agency, Wagramer Strasse 5, PO Box 100, 1400 Vienna, Austria Immobilisation Science Laboratory, Department of Materials Science and Engineering, University of Sheffield, Mappin Street, Sheffield, S1 3JD, United Kingdom
R. O. Abdel Rahman
Affiliation:
Hot Laboratory Center, Atomic Energy Authority of Egypt, P.O. 13759, Inshas, Cairo, Egypt
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Abstract

An overview is given on research activities on cementitious materials for radioactive waste management systems based on the IAEA Coordinated Research Project (CRP) held in 2007-2010. It has been joined by 26 research organizations from 22 countries which shared their research and practical activities on use of cementitious materials for various barrier purposes. The CRP has initially formulated the research topics considered within four specific streams: A) Conventional cementitious systems; B) Novel cementitious materials and technologies; C) Testing and waste acceptance criteria; and D) Modelling long term behaviour.

The CRP has analysed both barrier functions and interactions envisaged between various components with focus on predisposal stage of waste management. Cementation processes have achieved a high degree of acceptance and many processes are now regarded as technically mature. A large body of information is currently available on proven waste conditioning technologies although novel approaches are continuing to be devised.

Most of the existing technologies have been developed for conditioning of large amounts of operational radioactive waste from nuclear power plants and other nuclear fuel cycle facilities. However new waste streams including those resulting from legacy and decommissioning activities required improved material performance and technologies.

The most important outcome of CRP was the exchange of information and research co-operation between different institutions and has contributed towards general enhancement of safety by improving waste management practices and their efficiency. The paper presents the most important results and trends revealed by CRP participants. The research contributions of participating organizations will be published as country contributions in a forthcoming IAEA technical publication.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-il06
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

1. IAEA. Performance of engineered barrier materials in near surface disposal facilities for radioactive waste , TECDOC-1255, IAEA, Vienna (2001).Google Scholar
2. IAEA. CRP on Behaviors of Cementitious Materials in Long Term Storage and Disposal. http://www.iaea.org/OurWork/ST/NE/NEFW/wts_crp_cement.html (2010).Google Scholar
3. Drace, Z., Ojovan, M.I.. The behaviours of cementitious materials in long term storage and disposal: an overview of results of the IAEA coordinated research programme. Mater. Res. Soc. Symp. Proc. 1193, 663–672 (2009).10.1557/PROC-1193-663Google Scholar
4. Glasser, F.P.. Application of inorganic cements to the conditioning and immobilisation of radioactive wastes. In: Handbook of advanced radioactive waste conditioning technologies , Edited by Ojovan, M I. Pp. 67–135, Woodhead, Oxford (2011).10.1533/9780857090959.1.67Google Scholar
5. Ojovan, M.I., Varlackova, G.A., Golubeva, Z.I., Burlaka, O.N.. Long-term field and laboratory leaching tests of cemented radioactive wastes. J. Hazard. Mater., 187, 296–302 (2011).10.1016/j.jhazmat.2011.01.004Google Scholar
6. IAEA. Strategy and methodology for radioactive waste characterization . IAEA TECDOC-1537, IAEA, Vienna (2007).Google Scholar
7. IAEA, Safety Assessment Methodologies for Near Surface Disposal Facilities, Results of a coordinated research project, Volume 1 Review and enhancement of safety assessment approaches and tools , IAEA, Vienna (2004).Google Scholar
8. Walton, J.C., Plansky, L.E., Smith, R.W., Models for estimation of service life of concrete barriers in low-level radioactive waste disposal NUREG/CR-5542 EGG-2597, 1990.10.2172/6548946Google Scholar
9. Abdel Rahman, R.O., Zaki, A.A., Assessment of the leaching characteristics of incineration ashes in cement matrix, Chem Eng J., 155 (2009) 698–708.10.1016/j.cej.2009.09.002Google Scholar
10. Suzuki, Kazuyuki, Ono, Yoshiro, Leaching characteristics of stabilized/solidified fly ash generated from ash-melting plant, Chemosphere, 71 (2008) 922–932.Google Scholar
11. Geankoplis, C.J., Principles of unsteady-state and convective mass transfer , In: Betty, S. (Ed.) Transport processes and unit operations, Englewood Cliffs, NJ, 1993 Google Scholar
12. Abdel Rahman, R.O., (2005) Performance Assessment of Unsaturated Zone as a Part of Waste Disposal Site, PhD thesis, Faculty of Engineering Alexandria University, Egypt.Google Scholar
13. Richard, L.A., 1931, “Capillary Conduction of Liquid Through Porous Medium”, physics, 1: 318–333 10.1063/1.1745010Google Scholar
14. McGrail, P., Bacon, D.H., Meyer, P.D., Ojovan, M.I., Strachan, N.V. Ojovan, I.V. Startceva. New developments in field studies of low activity waste glass corrosion and contaminant transport. Mat. Res. Soc. Symp. Proc. 757, II2.1.1–13 (2003).Google Scholar