Hostname: page-component-7479d7b7d-jwnkl Total loading time: 0 Render date: 2024-07-11T23:17:51.590Z Has data issue: false hasContentIssue false
  • English
  • Français

Radionuclide Transport Calculations in the Safety Assessment SR 97

Published online by Cambridge University Press:  21 March 2011

M. Lindgren  and
F. Lindström
M. Lindgren
Affiliation:
Kemakta Consultants Co., Box 12655, S-112 93 Stockholm (Sweden)
F. Lindström
Affiliation:
Swedish Nuclear Fuel and Waste Management Co. (SKB), Box 5864, S-102 48 Stockholm (Sweden)
Get access

Abstract

This study treats radionuclide transport calculations for a canister defect scenario in the safety assessment SR 97, which concerns a deep repository for spent nuclear fuel of the KBS-3 type in Sweden. The aims of the calculations are to:

Quantitatively describe the radionuclide transport.

Show the impact of uncertainty in input data and show which parameters govern the calculated release rates.

Compare three different real sites in Sweden (Aberg, Beberg and Ceberg) with each other and with dose limits given in Swedish regulations (none of the sites is considered in the on-going localization process). Only briefly described in this paper.

Illustrate the impact of the different barriers in the system.

Deterministic calculations illustrate the radionuclide transport for reasonable conditions. Uncertainty cases show the influence of the uncertainty for data related to different parts of the repository system by systematically giving them pessimistic values while all others are reasonable. Simplified probabilistic calculations have also been performed.

The analysis shows that the most important parameters in the near field are the number of defective canisters and the instant release fraction. In the far field the most important uncertainties affecting release and retention are connected to permeability and connectivity of the fractures in the rock. The dose rate in the biosphere is essentially controlled by the possibilities of dilution.

The calculated maximum doses for the hypothetical repositories are well below the dose limits, and hence they meet the acceptance criteria for a deep repository for spent fuel.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 773
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. SR 97 -Post closure safety, Volume I and II, SKB Technical report TR-99-06, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar
2. Lindgren, M. and Lindström, F., SR 97 - Radionuclide transport calculations, SKB Technical report TR-99-23, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar
3. Walker, D. and Gylling, B., Site-scale groundwater flow modelling of Aberg, SKB Technical report TR-98-23, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1998.Google Scholar
4. Gylling, B., Walker, D. and Hartley, L., Site-scale groundwater flow modelling of Beberg, SKB Technical report TR-99-18, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar
5. Walker, D. and Gylling, B., Site-scale groundwater flow modelling of Ceberg, SKB Technical report TR-99-13, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar
6. Romero, L., Thompson, A., Moreno, L., Neretnieks, I., Widén, H. and Boghammar, A., COMP23/NUCTRAN User's Guide, SKB report R-99-64, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar
7. Norman, S. and Kjellbert, N., FARF31- A far field radionuclide migration code for use in the PROPER package, SKB Technical report TR 90-01, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1990.Google Scholar
8. Nordlinder, S., Bergström, U. and Mathiasson, L., Ecosystem specific dose conversion factors for Aberg, Beberg and Ceberg, SKB Technical report TR-99-15, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar
9. Andersson, J., SR 97 - Data and data uncertainties - Compilation of data and data uncertainties for radionuclide transport calculations, SKB Technical report TR-99-09, Swedish Nuclear fuel and Waste Management Co, Stockholm, Sweden, 1999.Google Scholar