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The Near-Field Transport Code Tullgarn and its Use in Performance Assessment

Published online by Cambridge University Press:  01 January 1992

Patrik Sellin  and
Nils Kjellbert
Patrik Sellin
Affiliation:
Swedish Nuclear Fuel and Waste Management Company, Stockholm, Sweden
Nils Kjellbert
Affiliation:
Swedish Nuclear Fuel and Waste Management Company, Stockholm, Sweden
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Abstract

The near-field radionuclide migration code Tullgarn has been developed for performance assessment purposes. As a part of the PROPER-code package it has been successfully applied in the SKB 91 safety analysis.

The features and processes included in the code are:

  • - Radioactive chain decay

  • - Different canister failure mechanisms (copper corrosion from sulphide attack, steel corrosion, internal overpressure and initially defective canisters) - Spent fuel dissolution. The model is based on the assumption that the dissolution rate is proportional to the α-dose rate

  • - Transport calculations are done with a resistance-network model. Tullgarn calculates the stationary release of radionuclides from a defect in the canister through the buffer and out into a fracture in the rock or up to the damaged zone under the deposition tunnel.

Tullgarn can be used as a stand-alone model for near-field release calculations or as a submodel in an integrated assessment. In the SKB 91 analysis, Tullgarn gave the source term to the far-field model.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 294: Symposium V – Scientific Basis for Nuclear Waste Management XVI , 1992 , 725
Copyright
Copyright © Materials Research Society 1993

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References

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