Hostname: page-component-76fb5796d-wq484 Total loading time: 0 Render date: 2024-04-26T03:58:17.078Z Has data issue: false hasContentIssue false
  • English
  • Français

The Role of Engineered Barriers in the Performance Assessment of a Repository for L/ILW

Published online by Cambridge University Press:  10 February 2011

M.M. Askarieh ,
A.N. Chambers ,
G.E. Hickford  and
S.M. Sharland
M.M. Askarieh
Affiliation:
United Kingdom Nirex Limited, Curie Avenue, Harwell, Didcot, Oxon OX11 0RH, UK
A.N. Chambers
Affiliation:
AEA Technology, 424 Harwell, Didcot, Oxon OX11 ORA, UK
G.E. Hickford
Affiliation:
United Kingdom Nirex Limited, Curie Avenue, Harwell, Didcot, Oxon OX11 0RH, UK
S.M. Sharland
Affiliation:
AEA Technology, 424 Harwell, Didcot, Oxon OX11 ORA, UK
Get access

Abstract

Designs for repositories for the underground disposal of radioactive waste throughout the world are generally based on the ‘multiple barrier’ concept. This comprises engineered barriers that are the introduced features of the disposal facility, and natural barriers provided by the host geology. In the near field of the repository, the engineered barriers can provide both physical and chemical containment. This paper is mainly concerned with the deep disposal of intermediatelevel and low-level waste. In particular, it reviews current understanding concerning the evolution of the chemical and physical barriers for the disposal concept developed by United Kingdom Nirex Limited. Examples of work from underlying research programmes that support this understanding are discussed. The paper also discusses the representation of the engineered barriers in performance assessment calculations.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 465
Copyright
Copyright © Materials Research Society 1998

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

1 Review of Radioactive Waste Management Policy: Final Conclusions, UK Government White Paper Cm 2919, HMSO, 1995.Google Scholar
2 Nirex Deep Waste Repository: Scientific Update 1993, Nirex Report No. 525, 1993.Google Scholar
3 Post-closure Performance Assessment: Approach to Model Development, Nirex Science Report S/95/010, 1995.Google Scholar
4 SKB 91. Final Disposal of Spent Nuclear Fuel. Importance of the Bedrock for Safety., SKB Technical Report 92-20, 1992.Google Scholar
5 Research and Development on Geological Disposal of High-level Radioactive Waste: First Progress Report, PNC Report No. PNC TN1410 93-059, 1992.Google Scholar
6 Beurteilung der Langzeitsicherheit des Endlagers SMA am Standort Wellenberg (Gemeinde Wolfenschiessen, NW), Nagra Technical Report NTB 93-26, 1993.Google Scholar
7 Post-closure Performance Assessment: Near-field Evolution, Nirex Science Report S/95/009, 1995.Google Scholar
8 Nirex Near Field Research: Report on Current Status in 1994, Nirex Science Report S/95/011, 1995.Google Scholar
9 Hudson, J.A., Rock Engineering Systems: Theory and Practice, Ellis Horwood Ltd, Chichester, 1992.Google Scholar
10 Nirex Gas Generation and Migration Research: Report on Current Status in 1994, Nirex Science Report S/96/002, 1996.Google Scholar
11 Atkinson, A., Harris, A.W. and Hearne, J.A., Comparison of Materials for the Backfilling of Repositories, Nirex Report NSS/R306, Draft 1997.Google Scholar
12 Ebert, W.L. and Mazer, J.J. in Scientific Basis for Nuclear Waste Management XVII, edited by Barkatt, A. and Konynenburg, R.A. Van (Mater.Res.Soc.Symp.Proc. 333, Pittsburg, PA 1994), p. 27–40.Google Scholar
13 Nirex 95: A Preliminary Analysis of the Groundwater Pathway for a Deep Repository at Sellafield Volume 3 - Calculations of Risk, Nirex Science Report S/95/012, 1995.Google Scholar
14 The United Kingdom Radioactive Waste Inventory, Nirex Report No. 695, 1996.Google Scholar
15 Repository for Radioactive Waste - Vault Backfill United Kingdom Nirex Limited International Patent Application No. PCT/GB94/01625, Filing date 28 July 1994.Google Scholar
16 Marsh, G.P., Taylor, K.J., Sharland, S.M. and Tasker, P.W. in Scientific Basis for Nuclear Waste Management X, edited by Bates, K. and Seefeldt, W.B. (Mater.Res.Soc.Symp.Proc. 84, Pittsburg, PA, 1987), p. 227–238.Google Scholar
17 Porter, F.M. and Chambers, A.V., The Development and Application of RARECAN Nirex Report NSS/R396, 1995.Google Scholar
18 Chambers, A.V., Gould, L.J., Hoek, J. and Thompson, A.M., The Development and Application of STRAW2, Nirex Science Report, Draft 1997.Google Scholar
19 Harris, A.W. and Nickerson, A.K., An Assessment of the Mass-transport Properties of Cementitious Materials under Water-saturated Conditions, Nirex Report NSS/R309, 1995.Google Scholar
20 Chambers, A.V. in Modelling Radionuclide Transport in Cracks Through Cementitious Radioactive Waste, edited by Murakami, T. and Ewing, R.C., (Mater.Res.Soc.Symp.Proc. 353, Pittsburgh, PA, 1995), p. 891–899.Google Scholar
21 Haworth, A., Smith, T.G. and Tweed, C.J., HARPHRQ: A Computer Program for Geochemical Modelling, Nirex Report NSS/R380, 1995.Google Scholar
22 Goldberg, J.E., Gould, L.J., Heath, T.G., Thompson, A.M. and Tweed, C.J., Development of Methodology for Modelling the Redox Chemistry of the near field of a Cementitious Radioactive Waste Repository, Nirex Report NSS/R398, 1995.Google Scholar
23 Bond, K.A., Moreton, A.D. and Tweed, C.J., Water Compositions of Relevance to a Deep Cementitious-based Repository at Sellafield: Re-calculation using Thermodynamic Modelling, Nirex Report NSS/R310, 1995.Google Scholar
24 Berner, U.R., Radiochim. Acta 44/45, p. 387 (1988).Google Scholar
25 Harris, A.W., Atkinson, A., Cole, G.B., Haworth, A., Nickerson, A.K. and Smith, A.C., The Performance of Cementitious Barriers in Repositories, Nirex Report NSS/R389, Draft 1997.Google Scholar
26 Haworth, A. and Smith, A.C., Improvements to the Coupled Chemical Equilibria and Transport Code CHEQMATE, Nirex Report NSS/R324, 1992.Google Scholar
27 Greenberg, S.A. and Chang, T.N., J.Phys.Chem. 69, p. 1151 (1965).Google Scholar
28 Atkinson, A., Buffering of pH in an Inhomogeneous Repository, Nirex Report NSS/R287, 1995.Google Scholar
29 Miodowski, A.E., Nancarrow, P.H.A. and Spiro, B., A Mineralogical and Stable Isotope Study of Natural Analogues of Ordinary Portland Cement (OPC) and CaO-Si02-H20 (C-S-H) Compounds, Nirex Report NSS/R240, 1991.Google Scholar
30 Atkinson, A., Harris, A.W. and Hearne, J.A., Hydrothermal Alteration and Ageing of Synthetic Calcium Silicate Hydrate Gcls, Nirex Report NSS/R374, 1995.Google Scholar
31 Sinclair, J.E. and Agg, P.J., MASCOT and MOP Programs for Probabilistic Safety Assessment, Nirex Report NSS/R336 (Parts A to K), 1994.Google Scholar
32 Post-closure Performance Assessment: Approach to Model Development, Nirex Science Report S/95/010, 1995.Google Scholar