Hostname: page-component-5c6d5d7d68-txr5j Total loading time: 0 Render date: 2024-08-21T17:59:51.936Z Has data issue: false hasContentIssue false

Repository Design Optimization for Long-Lived ILW

Published online by Cambridge University Press:  21 March 2011

I.G. McKinley
Affiliation:
Nagra (ISP), Hardstrasse 73, 5430 Wettingen, Switzerland, Email: [email protected]
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: [email protected]
F.B. Neall
Affiliation:
Neall Consulting Ltd., 23 Howe Bank Close, Kendal, LA9 7PU, United Kingdom, Email: [email protected]
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, [email protected]
Get access

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.

Type
Research Article
Copyright
Copyright © Materials Research Society 2001

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.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, pp1324 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), pp3549 Google Scholar