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Data Reduction for Radionuclide Transport Codes Used in Performance Assessments: An Example of Simplification Process

Published online by Cambridge University Press:  10 February 2011

B. Dverstorp
Affiliation:
Swedish Nuclear Power Inspectorate, SKI, Stockholm, Sweden
B. Mendes
Affiliation:
Department of Physics, Stockholm University
A. Pereira
Affiliation:
Department of Physics, Stockholm University
B. Sundström
Affiliation:
Swedish Nuclear Power Inspectorate, SKI, Stockholm, Sweden
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Abstract

The input data required for transport models for use in long-term risk assessments of repositories for radioactive waste, in geological media, are intrinsic to the performance of the models. The flow parameters utilized in these models typically come from 2 or 3D hydro-geological calculations done in a prior phase of an assessment. This paper examines some of the standard simplifications introduced when hydrogeological data are reduced to ID as is often required for radionuclide transport models. Two key aspects of data reduction are the determination of average properties of fractured media between and along transport pathways. To quantify possible errors associated with these reduction procedures, two computer experiments have been done. We show that the use of effective flow parameters, representing the average properties of a set of independent transport pathways, in a 1 D radionuclide transport model can result in an underestimation of peak releases by one order of magnitude or more. This result is valid for short-lived nuclides whenever retardation is an important factor. On the other hand, averaging of spatially varying transport properties along a transport pathway may lead to unjustified conservatism. A simple calculation example using Monte Carlo technique, shows that a model that does not take into account spatially varying retardation properties along the transport pathways may overestimate peak release rates by several orders of magnitude. We conclude that more sophisticated transport models taking into account available hydrogeological information on spatial variability are needed to fully understand the potential errors associated with consequence calculations in the performance assessment

Type
Research Article
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

1 SKB 91, Final disposal of spent nuclear fuel. Importance of the bedrock for safety. 1992. SKB Technical Report 92-20, Sweden.Google Scholar
2 TVO-92, Safety Analysis of Spent Fuel Disposal, 1992. Report YJT-92-33 E, Finland.Google Scholar
3 SKI Site-94, Deep Repository Performance Assessment Project, 1996. SKI Report 96:36, Sweden.Google Scholar
4 , Kristallin-I, Safety Assessment Report, 1994. Nagra Technical Report 93-22, Switzerland.Google Scholar
5 Worgan, K. and Robinson, P. (1995). The CRYSTAL Geosphere Transport Model: Technical Documentation version 2.1. SKI Report 95:55, Stockholm, Sweden.Google Scholar
6 Neretnieks, I., Abelin, H. and Birgersson, L., 1987. Some recent observations of channeling in fractured rocks - Its potential impact on radionuclide migration. In: U.S. Dep. Energy -At. Energy Can. Lab. Conf., Sept 15-17, 1987, San Francisco, CA, Proc., pp. 387410.Google Scholar
7 Tsang, Y. W., Tsang, C. F. Hale., F. V. and Dverstorp, B., 1996. Tracer transport in stochastic continuum model of fractured media. Water Resources Research, Vol. 32, No. 10, pages 30773092, October 1996.Google Scholar