Coupled THM modelling of engineered barriers for the final disposal of spent nuclear fuel isolation

Author:

Toprak Erdem1,Olivella Sebastia2,Pintado Xavier3

Affiliation:

1. International Centre for Numerical Methods in Engineering (CIMNE), Universidad Politécnica de Cataluña, Campus Norte UPC, 08034 Barcelona, Spain

2. Department of Geotechnical Engineering and Geosciences, Universidad Politécnica de Cataluña, Campus Norte UPC, 08034 Barcelona, Spain

3. B+TECH Oy, Laulukuja 4, 00420 Helsinki, Finland

Abstract

AbstractThis paper describes the thermohydromechanical (THM) simulation of engineered barrier systems (EBS) for the final disposal of nuclear spent fuel in Finland. The bentonite barriers were simulated with the Barcelona Basic Model and the model was calibrated from laboratory tests. The evolution of gap closure and the presence of a fracture intersecting the disposal were analysed. The simulations were performed in 2D axisymmetrical geometries. Full 3D simulations were carried out in order to check the effect of the third dimension. The time required for the barriers to reach full saturation, the maximum temperature, deformations and displacements at the buffer–backfill interface and the homogenization of components both locally and globally are the main interests. The effect of rock fracture and the hydraulic conductivity of the rock are subjected to 2D sensitivity analyses.

Publisher

Geological Society of London

Subject

Geology,Ocean Engineering,Water Science and Technology

Reference21 articles.

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2. A constitutive model for partially saturated soils

3. Börgesson L. , Fredrikson A. & Johannesson L.-E. 1994. Heat Conductivity of Buffer Materials. SKB TR 94-29. Svensk Kärnbränslehantering AB (SKB), Stockholm, Sweden, http://www.skb.com/publication/11249/TR94-29.pdf

4. Hagros A. , Aikas K. , McEvven T. & Anttila P. 2003. Host Rock Classification. Working Report 2003-04. Posiva, Eurajoki, Finland, http://www.posiva.fi/files/2183/POSIVA-2003-04_Working-report_web.pdf

5. Hökmark H. , Lönnqvist M. , Kristensson O. , Sundberg J. & Hellström G. 2009. Strategy for Thermal Dimensioning of the Final Repository for Spent Nuclear Fuel. SKB Report R-09-04. Svensk Kärnbränslehantering AB (SKB), Stockholm, Sweden.

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