We develop a numerical scheme to study the time and space distribution of the 90Sr concentration in a fictitious accident in which 90Sr is leaking into fully saturated surroundings from a package situated in a simplified model of a low- or intermediate-level waste repository. The repository contains three barriers: a concrete envelope, plain concrete, and host rock. Diffusion is considered as the primary transport mechanism, and adsorption 90Sr to pore walls is taken into account. We choose three locations, one in each barrier, to monitor the 90Sr concentrations over the time span of 2000 years. We conclude that concentration 90Sr decays so fast in the barriers that it does not penetrate to the environment and should not present any health risk.
Numerical assessment of radionuclide leakage in a low or intermediate level waste geological repository
Jiří Maděra, Jaroslav Kruis, Igor Medved’; Numerical assessment of radionuclide leakage in a low or intermediate level waste geological repository. AIP Conf. Proc. 24 November 2020; 2293 (1): 190006. https://doi.org/10.1063/5.0027089
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