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An introduction to package evolution and criticality research studies relevant to the UK disposal programme

Published online by Cambridge University Press:  05 July 2018

C. Padovani*
Affiliation:
Nuclear Decommissioning Authority, Radioactive Waste Management Directorate, NDA Harwell Office, Building 587, Curie Avenue, Harwell, Didcot, Oxfordshire OX11 0RH, UK
S. J. Williams
Affiliation:
Nuclear Decommissioning Authority, Radioactive Waste Management Directorate, NDA Harwell Office, Building 587, Curie Avenue, Harwell, Didcot, Oxfordshire OX11 0RH, UK
P. Wood
Affiliation:
Nuclear Decommissioning Authority, Radioactive Waste Management Directorate, NDA Harwell Office, Building 587, Curie Avenue, Harwell, Didcot, Oxfordshire OX11 0RH, UK
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Abstract

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In the UK, radioactive wastes currently planned for disposal in a geological disposal facility (GDF) include intermediate level waste, some low level waste and high level waste. Disposal of other materials, including spent fuel, uranium and plutonium is also being evaluated to inform the safety case for a GDF, if such materials were to be classified as wastes in the future. This paper describes the generic safety functions through which waste packages can contribute to the safety case of a GDF in the UK. It describes the engineering approach used or envisaged, in the UK and internationally, to ensure that waste packages retain their safety functions for the required periods of time and summarizes the scientific basis underpinning the current understanding of relevant evolution processes. Where gaps in the knowledge exist, the Nuclear Decommissioning Authority Radioactive Waste Management Directorate has identified specific research activities needed to close out such gaps to a level of maturity sufficient for this stage of the disposal programme (generic). This paper describes the latest results from their R&D programme and presents a summary of the research activities planned to meet the current needs of the disposal programme with specific reference to the topics of package evolution and criticality safety.

Type
Research Article
Creative Commons
Creative Common License - CCCreative Common License - BY
© [2012] The Mineralogical Society of Great Britain and Ireland. This is an open access article distributed under the terms of the Creative Commons Attribution (CC BY) licence (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
Copyright
Copyright © The Mineralogical Society of Great Britain and Ireland 2012

References

Albores-Silva, O. (2011) Atmospheric stress corrosion cracking and pitting of austenitic stainless steel. Unpublished PhD thesis, Newcastle University, Newcastle-upon-Tyne, UK.Google Scholar
Albores-Silva, O., Charles, E.A. and Padovani, C. (2011) Effect of chloride deposition on stress corrosion behaviour of 316L stainless steel used for intermediate level radioactive waste containers. Corrosion Engineering, Science an. Technology, 46, 124128.Google Scholar
Anonymous (2007) Proceedings of the 8th International Conference on Nuclear Criticality Safety. St Petersburg, Russia, 28 May to 1 June.Google Scholar
Anonymous (2011) Proceedings of the 9th International Conference on Nuclear Criticality Safety. Edinburgh, United Kingdom, 1922.September .Google Scholar
Cronin, J. and Collier, N. (2011) Corrosion and Expansion of Grouted Magnox. National Nuclear Laboratory report NNL (11) 11524.Google Scholar
Dawson, J., Baston, G., Cowper, M.M. and Marshall, T.A. (2010) The Effects of Gamma Irradiation and Thermal Ageing on the Stability of Candidate Polymer Encapsulants. Serco report SERCO/TAS/ 002008/001 Issue 02.Google Scholar
Department for Environment Fisheries and Rural Affairs (DEFRA), Department for Business, Enterprise and Regulatory Reform (BERR) and the Devolved Administration for Wales and Northern Ireland. (2008) Managing Radioactive Waste Safely: A Framework for Implementing Geological Disposal. DEFRA, London, 100 pp.Google Scholar
Deissmann, G., Neumeirer, S., Modolo, G. and Bosbach, D. (2011) Review of the durability of potential plutonium waste forms under conditions relevant to geological disposal. Report by FZ Julich for the NDA.Google Scholar
Ghahari, S.M. (2012) In Situ Synchrotron X-ray Characterisation and Modelling of Pitting Corrosion of Stainless Steel. Unpublished PhD thesis, University of Birmingham, Birmingham, UK..Google Scholar
Ghahari, S.M., Krouse, D.P., Laycock, N.J., Rayment, T., Padovani, C., Suter, T., Mokso, R., Marone, F., Stampanoni, M., Monir, M. and Davenport, A.J. (2011) Pitting corrosion of stainless steel: measuring and modelling pit propagation in support of damage prediction for radioactive waste containers. Corrosion Engineering, Science an. Technology, 46, 205211.Google Scholar
Harrison, M. (2010) Review of Glass Dissolution rates for use in the Disposal System Safety Case Performance Assessment Models. National Nuclear Laboratory report NNL (10) 10734, Issue 3.Google Scholar
Karney, G. and Thetford, R. (2011) Overview of the UK Spent Fuel Inventory - Evaluation of the Instant Release Fraction. Serco report Serco/TAS/ E.004027.02 Issue 4.Google Scholar
King, F. and Watson, S. (2010) Review of the corrosion performance of selected metals as canister materials for UK spent fuel and/or HLW. Quintessa Report QRS-1384J-1.Google Scholar
King, F., Watson, S., Wilson, J. and Mackenzie, J. (2011) Corrosion of candidate HLW/spent fuel container materials in generic environments - operational aspects. Quintessa report QRS-1525A-R1.Google Scholar
Kursten, B. and Druyts, F. (editors) (2011) Proceedings of the 4th international workshop on long-term prediction of corrosion damage in nuclear waste systems. Corrosion Engineering, Science and Technology, 46(2).CrossRefGoogle Scholar
L’Hostis, V., Gens, R. and Gallé, C. (editors) (2009) Long-Term Performance of Cementitious Barriers and Reinforced Concrete in Nuclear Power Plants and Waste Management. Proceedings of the RILEM workshop NUCPERF 2009, PRO 64.Google Scholar
Mansur, L.K., Ishino, S., Lemaignan, C. and Werme, L.O. (editors) (2008) Proceedings of the third international workshop on long-term prediction of corrosion damage in nuclear waste systems. Journal of Nuclear Materials, 379.Google Scholar
Mason, R.M., Smith, P.N., Sweet, D.W., Eaton, M.D., Goddard, A.J.H., Gomes, J.L.M.A. and Pain, C.C. (2009) A Summary of Verification, Validation, Benchmarking, Uncertainty and Sensitivity for the FETCH, QSS and RTM Computer Models. Serco report SERCO/TAS/P3648/W001 Issue 2.Google Scholar
Mason, R.M., Martin, J.K., Smith, P.N. and Turland, B.D. (2012) Comparison of a post-closure transient criticality model with the Oklo natural reactors. Mineralogical Magazine, 76, 31453153.CrossRefGoogle Scholar
Mignanelli, M. and Rossiter, G. (2011) The characteristics of LWR fuel at high burn-up and their relevance to AGR spent fuel. National Nuclear Laboratory report NNL (10) 10930, Issue 2.Google Scholar
Morris, J.E. and Winpenny, D.B. (2012) The Atmospheric Corrosion of Ductile Cast Iron. AMEC report to NDA RWMD 17391-TR-003. Nuclear Decommissioning Authority (2010a) Geological Disposal: Package Evolution Status Report. NDA Report NDA/RWMD/031.Google Scholar
Nuclear Decommissioning Authority (2010b) Geological Disposal: Criticality Safety Status Report. NDA Report NDA/RWMD/038.Google Scholar
Nuclear Decommissioning Authority (2010c) Geological Disposal: Generic Transport Safety Case Main Report. NDA Report NDA/RWMD/019.Google Scholar
Nuclear Decommissioning Authority (2010d) Geological Disposal: Generic Operational Safety Case Main Report. NDA Report NDA/RWMD/020.Google Scholar
Nuclear Decommissioning Authority (2010e) Geological Disposal: Generic Environmental Safety Case Main Report. NDA Report NDA/RWMD/021.Google Scholar
Nuclear Decommissioning Authority (2011) Geological Disposal: R&D Programme Overview - Research and Development Needs in the Preparatory Studies Phase. NDA Report NDA/RWMD/073.Google Scholar
Nuclear Decommissioning Authority (2012) Robust Interim Storage of Higher Activity Waste Packages - Integrated Approach, issue 2.Google Scholar
Qaim, S.M. (editor) (2008) Proceedings of the Migration 2007. Radiochimica Acta, 96(911..Google Scholar
Stanley, S.J. (2010) Development of innovative solutions to monitor radioactive waste packages in order to validate long-term behaviour and performance. National Nuclear Laboratory report NNL (09) 10 730, issue 2.Google Scholar
Utton, C. and Godfrey, I.H. (2010) Review of stability of cement-grouted IX materials, sludges and flocs. National Nuclear Laboratory report NNL (09) 10212.Google Scholar
Utton, C., Hand, R., Hyatt, N. and Swanton, S. (2011) Glass durability in high pH environments: A review of the literature. Serco report SERCO/TAS/03133/ 001.Google Scholar
Van Iseghem, P. (editor) (2006) Scientific Basis for Waste Disposal, volume XXIX. Materials Research Society Symposium Proceedings, 932.Google Scholar
Winsley, R.J., Smart, N.R., Reddy, B., Rance, A.P. and Fennel, P.A.H. (2011a) 4 Metre Box Monitoring Programme - Results for Period 2007-2010. Serco report SERCO/TCS/000730.01.Google Scholar
Winsley, R.J., Fennel, P.A.H., Smart, N.R., Reddy, B. and Rance, A.P. (2011b) Experimental study to evaluate the effect of polymeric encapsulants on the corrosion resistance of ILW packages. Serco report SERCO/TS/MCRL/E.003314.Google Scholar
Winsley, R.J., Smart, N.R. and Padovani, C. (2012) Experimental study to evaluate the effect of polymeric encapsulants on the corrosion resistance of intermediate-level radioactive waste packages. Mineralogical Magazine, 76, 29572967.CrossRefGoogle Scholar