Hostname: page-component-cd9895bd7-7cvxr Total loading time: 0 Render date: 2024-12-27T10:20:09.529Z Has data issue: false hasContentIssue false

Deep borehole disposal of higher burn up spent nuclear fuels

Published online by Cambridge University Press:  05 July 2018

F. G. F. Gibb*
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science & Engineering, University of Sheffield, Sheffield S1 3JD, UK
K. P. Travis
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science & Engineering, University of Sheffield, Sheffield S1 3JD, UK
K. W. Hesketh
Affiliation:
National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington, Cheshire WA3 6AE, UK
*
Rights & Permissions [Opens in a new window]

Abstract

Core share and HTML view are not available for this content. However, as you have access to this content, a full PDF is available via the ‘Save PDF’ action button.

The heat outputs of higher burn up spent fuels (SF) create problems for disposal in mined repositories, including needs for reduced container loadings and extended pre-disposal cooling. An alternative that is less temperature sensitive is deep borehole disposal (DBD) which offers safety, cost, security and other potential benefits and could be implemented relatively quickly using currently available deep-drilling technology. We have modified our previously proposed version of DBD to be more appropriate for higher burn-up fuels by using smaller (0.36 m diameter) stainless steel containers, a smaller (0.56 m diameter) borehole, and different support matrices. We present the results of new heat-flow modelling for DBD of UO2 and MOX SF with burn ups of 55 and 65 GWd/t showing how temperatures evolve, especially on the outer surface of the containers. Consequences for the performance of the support matrices and the disposal concept are discussed. The thermal modelling indicates DBD is a viable option for higher burn-up SF and could be a practical disposal route for many combinations of fuel types, burn ups, ages and container loadings. Further, the results suggest that DBD of complete fuel assemblies, a desirable option, would be feasible and require much shorter pre-disposal cooling than necessary for disposal in mined repositories.

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

Arnold, B.W., Swift, P.N., Brady, P.V., Orrell, S.A. and Freeze, G.A. (2010) Into the deep. Nuclear Engineering International, 2010, 1822.Google Scholar
Attrill, P.G. and Gibb, F.G.F. (2003) Partial melting and recrystallization of granite and their application to deep disposal of radioactive waste. Part 1 - rationale and partial melting. Lithos, 67, 103117.CrossRefGoogle Scholar
Best, M.G. (2003) Igneous and Metamorphic Petrology. Blackwell Science, Malden, Massachusetts, USA.Google Scholar
Beswick, J. (2008) Status of Technology for Deep Borehole Disposal. Report for the Nuclear Decommissioning Authority by EPS International, Contract No. NP01185.Google Scholar
Beswick, J. (2009) Deep borehole disposal of radioactive waste. Presentation to the 11th Radioactive Waste Immobilisation Network (RWIN) meeting, Sheffield, April 2009. [http://www.rwin.org.uk/presentations. html].Google Scholar
Blue Ribbon Commission (2012) Blue Ribbon Commission on America’s nuclear future. Report to the Secretary of Energy. US Department of Energy, Washington DC.Google Scholar
Brady, P.V., Arnold, B.W., Freeze, G.A., Swift, P.N., Bauer, S.J., Kanney, J.L., Rechard, R.P. and Stein, J.S. (2009) Deep Borehole Disposal of High Level Radioactive Waste. Sandia Report SAND20094401. Sandia National Laboratories, Albuquerque, New Mexico, USA.Google Scholar
Burstall, R.F. (1979) FISPIN - a Computer Code for Nuclide Inventory Calculations. ND-R 328(R). UK Atomic Energy Authority, Abingdon, Oxfordshire, UK.Google Scholar
Chapman, N. and Gibb, F. (2003) A truly final waste management solution. Radwaste Solutions, 10, 2637.Google Scholar
Gibb, F.G.F. (1999) High-temperature, very deep, geological disposal: a safer alternative for high-level radioactive waste. Waste Management, 19, 207211.CrossRefGoogle Scholar
Gibb, F.G.F. (2000) A new scheme for the very deep geological disposal of high-level radioactive waste. Journal of the Geological Society of London, 157, 2736.CrossRefGoogle Scholar
Gibb, F.G.F., McTaggart, N.A., Travis, K.P., Burley, D. and Hesketh, K.W. (2008a) High-density support matrices: key to deep borehole disposal of spent nuclear fuel. Journal of Nuclear Materials, 374, 370377.CrossRefGoogle Scholar
Gibb, F.G.F., Travis, K.P., McTaggart, N.A. and Burley, D. (2008b) A model for heat flow in deep borehole disposals of high-level nuclear wastes. Journal of Geophysical Research, 113, http://dx.doi.org/ 10.1029/2007JB005081.Google Scholar
Massachusetts Institute of Technology (2003) The Future of Nuclear Power: An Interdisciplinary MIT Study. Massachusetts Institute of Technology (MIT), Cambridge, Massachusetts, USA.Google Scholar
Nuclear Decommissioning Authority (2009) Geological Disposal Generic Design Assessment: Summary of Disposability Assessment for Wastes and Spent Fuel Arising from Operation of the Westinghouse AP1000. Nuclear Decommissioning Authority Technical Note 11339711.Google Scholar
Travis, K.P., Gibb, F.G.F. and Hesketh, K.W. (2012) Modelling deep borehole disposal of higher burn-up spent nuclear fuels. Materials Research Society, Symposium Proceedings, 1475, http://dx.doi.org/ 10.1557/opl.2012.605.CrossRefGoogle Scholar