High Performance Fvfe Multidomain Numerical Method to Perform Radionuclides Transport Calculations
نویسندگان
چکیده
This paper aims at describing numerical methods developed within the Melodie code to perform 3D saturated flow and transport calculations in the framework of radioactive waste geological repository. The diffusive type terms are discretised by a standard finite-element method and the convective term is treated with a Godunov-type finite-volume approach. The simulation domain is meshed using a structured tetrahedral mesh generator, which fulfils the Delaunay and cotangent criteria. In order to deal with a high number of computational nodes and different refinement levels, a domain decomposition strategy has been developed. As an example of the relevance of this numerical method we present calculations performed on the French “spent fuel / iron canisters / clay” concept designed by ANDRA in the frame of the feasibility study of a radioactive waste geological disposal. The analysis aims at assessing the influence of transfer properties of three radionuclides Se, Nb and I which differ in terms of solubility, sorption and chemical speciation.
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