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Repository Design Optimization for Long-Lived ILW

Published online by Cambridge University Press:  21 March 2011

I.G. McKinley ,
H. Kawamura ,
F.B. Neall  and
K. Ando
I.G. McKinley
Affiliation:
Nagra (ISP), Hardstrasse 73, 5430 Wettingen, Switzerland, Email: mckinleyi@nagra.ch
H. Kawamura
Affiliation:
Obayashi Corporation, Design Department No. 2, Civil Engineering Technical Division, Shinagawa Intercity B-Building, 2-15-2 Konan, Minato-ku, Tokyo 108-8502 - Japan, Email: kawamura@o-net.obayashi.co.jp
F.B. Neall
Affiliation:
Neall Consulting Ltd., 23 Howe Bank Close, Kendal, LA9 7PU, United Kingdom, Email: fiona.neall@btinternet.com
K. Ando
Affiliation:
Obayashi Corporation, Design Department No. 2, Civil Engineering Technical Division, Shinagawa Intercity B-Building, 2-15-2 Konan, Minato-ku, Tokyo 108-8502 - Japan, ando@o-net.obayashi.co.jp
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Abstract

From the point of view of clear demonstration of long-term safety, some of the long-lived intermediate-level wastes (ILW) are probably the most challenging of all waste types. Repository concepts for such wastes are reviewed with respect to optimization of operational procedures, post-closure performance, ease of making the safety case and costs. In particular, the advantages of designs incorporating a hydraulic cage and partitioning of wastes with different properties are discussed.

Information

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 843
Copyright
Copyright © Materials Research Society 2001

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References

REFERENCES

1.Nagra, 1985: “Projekt Gewähr 1985: Nuclear waste management in Switzerland - Feasibility studies and safety analysis - Summary”; Nagra Projekt Gewähr Report series NGB 85-09, Nagra, Baden, Switzerland.Google Scholar
2.TCO (TRU Coordination Office), 2000: Progress Report on the TRU waste disposal concept in Japan, JNC / FEPC report, JNC TY 14000 2000-002, TRU TR-2000-02Google Scholar
3.Nagra, 1994: Endlager für schwach- und mittelaktive Abfälle (Endlager SMA) - Bericht zur Langzeitsicherheit des Endlagers SMA am Standort Wellenberg (Gemeinde Wolfenschiessen, NW); Nagra Technical Report series, NTB 94-06, Nagra, Wettingen, SwitzerlandGoogle Scholar
4. Wiborgh, M., Bengtsson, A., Lindgreen, M., Pers, K., 1987: Radionuclide release from the near field in SFR; SFR 87-40, Svenks Kärnbränslesäkerhet AB, Stockholm, Sweden Google Scholar
5.SKB, 1999: SR 97 - Post closure safety; SKB TR-99-06, SKB, Stockholm, Sweden Google Scholar
6. Langmuir, D. & Apted, M.J., 1992: Backfill modification using geochemical principles to optimize high-level waste isolation in a geological repository; Mat. Res. Soc. Symp. Proc., 257, pp13–24 Google Scholar
7. Duerden, S.L., 1992: Review of the interaction between bentonite and cement; DOE Report DOE/HMIP/RR/92/031, Dept. of the Environment, London, UK Google Scholar
8. Bors, J. & Martens, R., 1992: The contribution of microbial biomass to the adsorption of radioiodine in soils; Journal of Environmental Radioactivity, 15(1), pp35–49 Google Scholar