Hostname: page-component-84b7d79bbc-2l2gl Total loading time: 0 Render date: 2024-07-26T08:44:51.444Z Has data issue: false hasContentIssue false

Building Confidence in Radionuclide Transport Models for Fractured Rock: The Nagra/JNC Radionuclide Retardation Programme

Published online by Cambridge University Press:  21 March 2011

K. Ota
Affiliation:
JNC (Japan Nuclear Cycle Development Institute), Tono Geoscience Centre, Toki, Gifu 509-5102, Japan. (kunio@tono.jnc.go.jp)
W.R. Alexander
Affiliation:
Nagra (National Co-operative for the Disposal of Radioactive Waste), 5430 Wettingen, Switzerland
P.A. Smith
Affiliation:
SAM (Safety Assessment Management Ltd), Bingham, Nottinghamshire NG13 8HQ, UK
A. Möri
Affiliation:
Geotechnical Institute, 3007 Bern, Switzerland
B. Frieg
Affiliation:
Nagra (National Co-operative for the Disposal of Radioactive Waste), 5430 Wettingen, Switzerland
U. Frick
Affiliation:
Nagra (National Co-operative for the Disposal of Radioactive Waste), 5430 Wettingen, Switzerland
H. Umeki
Affiliation:
JNC, Tokyo Office, Tokyo 100-8245, Japan
K. Amano
Affiliation:
JNC (Japan Nuclear Cycle Development Institute), Tono Geoscience Centre, Toki, Gifu 509-5102, Japan. (kunio@tono.jnc.go.jp)
M.M. Cowper
Affiliation:
AEA Technology, Harwell, Oxfordshire OX11 0RA, UK
J.A. Berry
Affiliation:
AEA Technology, Harwell, Oxfordshire OX11 0RA, UK
Get access

Abstract

The joint Nagra/JNC Radionuclide Retardation Programme has now been ongoing for 15 years with the main aim of direct testing of radionuclide transport models in as realistic a manner as possible. A large programme of field, laboratory and natural analogue studies has been carried out at the Grimsel Test Site in the central Swiss Alps and the Kamaishi In Situ Test Site in north-east Japan. The understanding and modelling of both the processes and the structures influencing radionuclide transport/retardation in fractured host rocks have matured as has the experimental technology, which has contributed to develop confidence in the applicability of the underlying research models in a repository performance assessment. In this paper, the successes and set-backs of this programme are discussed as is the general approach to the thorough testing of the process models and of model assumptions. In addition, a set of key findings is presented, involving discussions on the enhancement of confidence through the program.

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, Bericht zur Langzeitsicherheit des Endlagers SMA am Standort Wellenberg, Nagra Technical Report NTB 94-06 (Nagra, Switzerland, 1994).Google Scholar
2.JNC, H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan, JNC Technical Reports JNC TN1410 2000-001–2000-005 (JNC, Japan, 2000).Google Scholar
3. Alexander, W.R., Bradbury, M.H., McKinley, I.G., Heer, W., Eikenberg, J. and Frick, U., in Scientific Basis for Nuclear Waste Management XV (Mater. Res. Soc. Proc. 257, Pittsburgh, PA, 1992) pp.721728.Google Scholar
4. Frick, U., Alexander, W.R., Baeyens, B., Bossart, P., Bradbury, M.H., Bühler, Ch., Eikenberg, J., Fierz, Th., Heer, W., Hoehn, E., McKinley, I.G. and Smith, P.A., The Radionuclide Migration Experiment – Overview of Investigations 1985-1990, Nagra Technical Report NTB 91-04 (Nagra, Switzerland, 1992).Google Scholar
5. Smith, P.A., Alexander, W.R., Umeki, H., Mazurek, M., Heer, W., Baeyens, B., Bradbury, M.H., McKinley, I.G. and Kinzelbach, W., The Radionuclide Migration Experiment – Overview of Investigations 1990-1996, Nagra Technical Report NTB 00-09 (Nagra, Switzerland, in prep).Google Scholar
6. Umeki, H., Hatanaka, K., Alexander, W.R., McKinley, I.G. and Frick, U., in Scientific Basis for Nuclear Waste Management XVIII (Mater. Res. Soc. Proc. 353, Pittsburgh, PA, 1995) pp. 427434.Google Scholar
7. Heer, W. and Smith, P.A., in Scientific Basis for Nuclear Waste Management XXI (Mater. Res. Soc. Proc. 506, Pittsburgh, PA, 1998) pp.663670.Google Scholar
8. Pate, S.M., McKinley, I.G. and Alexander, W.R., in 5th CEC Natural Analogue Working Group Meeting and Alligator Rivers Analogue Project (ARAP) Final Workshop – Proceedings of an International Workshop held in Toledo, Spain, 5-9 October 1992, CEC Nuclear Science and Technology Series EUR15176EN (CEC, Luxembourg, 1994) pp.321331.Google Scholar
9. Alexander, W.R., Frieg, B., Ota, K. and Bossart, P., Nagra Bulletin No.27, 4355 (1996).Google Scholar
10. Eikenberg, J., Rüthi, M., Alexander, W.R., Frieg, B. and Fierz, T., in Scientific Basis for Nuclear Waste Management XXI (Mater. Res. Soc. Proc. 506, Pittsburgh, PA, 1998) pp.655662.Google Scholar
11. Frieg, B., Alexander, W.R., Dollinger, H., Bühler, C., Haag, P., Möri, A., and Ota, K., J. Contam. Hydrol. 35, 115130 (1998).Google Scholar
12. Ota, K., Amano, K. and Ando, T., in Proceedings of an International Workshop for the Kamaishi In Situ Experiments, Kamaishi, Japan, 24-25 August 1998, JNC Technical Report JNC TN7400 99-007 (JNC, Japan, 1999) pp.6776.Google Scholar
13.JNC, Final Report of Kamaishi In-situ Experiments, JNC Technical Report JNC TN7410 99-001 (JNC, Japan, 1999).Google Scholar
14. Bradbury, M.H. and Baeyens, B., in PSI Annual Report 1992, Annex IV (PSI, Switzerland, 1992) pp.5964.Google Scholar
15. Möri, A., Frieg, B., Ota, K. and Alexander, W.R., The In Situ Study of Safety Relevant Radionuclide Retardation in Fractured Crystalline Rock: Implications for Radionuclide Retardation in the Geosphere I, Nagra Technical Report NTB 00-07 (Nagra, Switzerland, in prep).Google Scholar
16. Nagra, Kristallin-I: Safety Assessment Report, Nagra Technical Report NTB 93-22 (Nagra, Switzerland, 1994).Google Scholar
17. Möri, A., Dollinger, H., Schild, M., Siegesmund, S., Vollbrecht, A., Adler, M., Mazurek, M., Frieg, B., Ota, K. and Alexander, W.R., The In Situ Study of Matrix Diffusion in Fractured Crystalline Rock: Implications for Radionuclide Retardation in the Geosphere II, Nagra Technical Report NTB 00-08 (Nagra, Switzerland, in prep).Google Scholar
18. Ota, K., Determination of In Situ Connected Porosity: Limitations in the Use of Laboratory-derived Diffusion Parameters, JNC Technical Report (JNC, Japan, in prep).Google Scholar
19. Vilks, P., Cramer, J.J., Melnyk, T.W., Stanchell, F.W., Miller, N.H. and Miller, H.G., In situ Diffusion in Granite: Phase I Final Report, Ontario Power Generation Report 06819-REP-01200-0087-R00 (OPG, Canada, 1999).Google Scholar