Testing Kd models of Cs + in the near field of a HLW repository in granite with a reactive transport model

Abstract

Performance assessment models of high-level radioactive waste (HLW) repositories commonly rely on the simplifying assumption of a constant K d for radionuclide sorption. Testing the validity of this assumption has been prevented by the lack of nuclide thermodynamic sorption data and the unavailability of models for handling nuclide migration and sorption together with the geochemical evolution of the near field. The validity of the constant K d assumption has been tested with a multicomponent reactive transport model (RTM) for Cs + in the near field of a HLW repository in granite. Model results show that the apparent K d of Cs +, K d a , increases with time due to the decrease of the ionic strength, I, of the bentonite porewater caused by the out-diffusion of the aqueous species from the bentonite into the granite. Computed values of I are related to those of K d a through the following polynomial expression: I = 253.5 1 K d a 2 + 8.77 1 K d a - 0.005 . A thermodynamic justification for such an expression has been derived from the cation exchange reactions. A constant- K d model fails to reproduce the release rate of Cs + from the near field computed with the RTM. A variable- K d model which incorporates the dependence of K d a on I reproduces adequately the Cs + release rate, thus providing a surrogate for the constant- K d model. The results of the sensitivity runs to changes in model parameters and boundary conditions show that the water flux at the bentonite–granite interface affects strongly the K d a through changes in I while the effective diffusion coefficient of the bentonite plays a minor role on K d a . An increase in the cation exchange capacity leads to an increase of K d a , but it does not affect the time evolution of I. Competing cations such as Ni 2+ and iron corrosion products decrease slightly the K d a of Cs + by competing for exchange sites and by increasing the I.