Solute transport properties of compacted Ca-bentonite used in FEBEX project.
The present Spanish concept of a deep geological high level waste repository includes an engineered clay barrier around the canister. The clay presents a very high sorption capability for radionuclides and a very small hydraulic conductivity, so that the migration process of solutes is limited by sorption and diffusion processes. Therefore, diffusion and distribution coefficients in compacted bentonite (i.e. in "realistic" liquid to solid ratio conditions) are the main parameters that have to be obtained in order to characterise solute transport that could be produced after the canister breakdown. Through-Diffusion (TD) and In-Diffusion (ID) experiments with HTO, Sr, Cs and Se were carried out using compacted FEBEX bentonite, which is the reference material for the Spanish concept of radioactive waste disposal. Experiments 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 hypotheses that do not hold in all the experiments. These experiments were interpreted also using an automatic parameter estimation code that overcomes the limitations of analytical solutions. Numerical interpretation allows the simultaneous estimation of porosity, diffusion and distribution coefficients, accounts for the role of porous sinters and time-varying boundary concentrations, and can use different types of raw concentration data.
García-Gutiérrez
M
M
CIEMAT, Ed. 20, Avenida Complutense 22, 28040 Madrid, Spain. michel@ciemat.es
Missana
T
T
Mingarro
M
M
Samper
J
J
Dai
Z
Z
Molinero
J
J
D000327:Adsorption; D001331:Automation; D001546:Bentonite; D002118:Calcium; D004058:Diffusion; D008962:Models, Theoretical; D011850:Radioactive Waste; D013030:Spain; D014316:Tritium; D018505:Waste Management / Q000379:methods*
D011850:Radioactive Waste; D014316:Tritium; D001546:Bentonite; D002118:Calcium