The present Spanish concept of a deep geological high level waste repositor
y includes an engineered clay barrier around the canister. The clay present
s a very high sorption capability for radionuclides and a very small hydrau
lic conductivity, so that the migration process of solutes is limited by so
rption and diffusion processes. Therefore, diffusion and distribution coeff
icients in compacted bentonite (i.e. in "realistic" liquid to solid ratio c
onditions) are the main parameters that have to be obtained in order to cha
racterise solute transport that could be produced after the canister breakd
own.
Through-Diffusion (TD) and In-Diffusion (ID) experiments with HTO, Sr, Cs a
nd Se were carried out using compacted FEBEX bentonite, which is the refere
nce material for the Spanish concept of radioactive waste disposal. Experim
ents were interpreted by means of available analytical solutions that allow
the estimation of diffusion coefficients and, in some cases, distribution
coefficients. Analytical solutions are simple to use, but rely on hypothese
s that do not hold in all the experiments. These experiments were interpret
ed also using an automatic parameter estimation code that overcomes the lim
itations of analytical solutions. Numerical interpretation allows the simul
taneous estimation of porosity, diffusion and distribution coefficients, ac
counts for the role of porous sinters and time-varying boundary concentrati
ons, and can use different types of raw concentration data. (C) 2001 Elsevi
er Science B.V. All rights reserved.