31 May 2021 to 4 June 2021
Europe/Berlin timezone

PORE-SCALE MODELLING IN SUPPORT OF SAFETY ASSESSMENT STUDIES FOR NUCLEAR WASTE REPOSITORIES IN FRACTURED ROCK

2 Jun 2021, 10:00
1h
Poster (+) Presentation (MS9) Pore-scale modelling Poster +

Speaker

Paolo Trinchero (Amphos 21)

Description

Safety assessment (SA) studies for spent nuclear fuel repositories in fractured rock entail the need to account for very large spatial and temporal scales. This is typically done by using continuum-based or Discrete Fracture Network (DFN)-based numerical simulations, which in turn rely on upscaled groundwater flow and transport parameters. However, model parameterisation is sometimes based on gross simplifications and there are still open questions such as: (i) what is the role of fracture filling minerals for flow channelling? (ii) what is the influence of mineral precipitation/dissolution processes on the evolution of flow channelling and on radionuclide transport including retention? and (iii) what is the impact of the altered rim zone bordering flowing fractures on radionuclide uptake by matrix diffusion? Here, we show how pore-scale simulations are used to address such questions and thus provide the basis for a more consistent derivation of effective parameters for use in large-scale SA simulations. The pore-scale models are based on a realistic yet synthetic single fracture that was generated using fractal theory1 and later imported followed by meshing using the open software OpenFOAM (http://www.openfoam.org). Calcite filling patches, which are typically found in field observations on drill-cores2, were subsequently generated using Sequential Indicator Simulations (SIS) carried out using the geostatistical software SGeMS3. Groundwater flow through the partly-filled fracture was computed using a Darcy-Brinkman-Stokes formulation4 and the ingress through the inlet of a slightly acidic unsaturated solution was simulated. The results show that the dissolution of calcite patches leads to a gradual increase of the fracture flow wetted surface area (i.e. the area of the fracture in contact with the flowing water) as well as a gradual increase of groundwater flow rates. In terms of retention capacity, due to diffusion in the matrix, the system shows a progressive decrease of the F-factor5 (i.e. the ratio between the flow wetted surface area and the groundwater flow rate), which is consistent with an alternative interpretation based on the integration of the transport resistance6 along transport pathways traced at different simulation times. We will also show the results of an on-going project, where a limited part of the fracture has been extracted and the bordering rock matrix included explicitly. The aim of this model is to study the effect of thin alteration rims on matrix diffusion processes.

References

(1) Stigsson, M. Structural Uncertainties of Rock Fractures and Their Effect on Flow and Tracer Transport. PhD Thesis, KTH, Sustainable development, Environmental science and Engineering, 2019.
(2) Löfgren, M.; Sidborn, M. Statistical Analysis of Results from the Quantitative Mapping of Fracture Minerals in Forsmark: Site Descriptive Modelling-Complementary Studies; R-09-30; Svensk kärnbränslehantering (SKB), 2010.
(3) Remy, N.; Boucher, A.; Wu, J. Applied Geostatistics with SGeMS: A User’s Guide; Cambridge University Press, 2009.
(4) Soulaine, C.; Roman, S.; Kovscek, A.; Tchelepi, H. A. Mineral Dissolution and Wormholing from a Pore-Scale Perspective. J. Fluid Mech. 2017, 827, 457–483. https://doi.org/10.1017/jfm.2017.499.
(5) SKB. Radionuclide Transport Report for the Safety Assessment SR-Site; TR-10-50; Svensk Kärnbränslehantering AB, Stockholm, Sweden., 2010.
(6) Cvetkovic, V.; Dagan, G. Transport of Kinetically Sorbing Solute by Steady Random Velocity in Heterogeneous Porous Formations. J. Fluid Mech. 1994, 265, 189–216.

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Primary authors

Paolo Trinchero (Amphos 21) Mr Aitor Iraola (Amphos 21) Dr Patrick Bruines ((2) Swedish Nuclear Fuel and Waste Management Company (SKB)) Dr Martin Stigsson ((2) Swedish Nuclear Fuel and Waste Management Company (SKB)) Dr Bjorn Gylling (Gylling GeoSolutions) Dr Jan-Olof Selroos (Swedish Nuclear Fuel and Waste Management Company (SKB))

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