Abstract
Swelling clays like bentonite are proposed as a buffer in high level nuclear waste repositories. An experimental device useful for thermo-hydraulic analysis of the samples behavior is outlined from room temperature to 373 K. The temperature distribution is established by axial heating of cylindrical samples. The spreading of the water content distribution is also determined from sample sections at the end of the run. An analytical model is build for steady states coherent with the experimental measurements. The transient temperature distribution and the final water content are also outlined via a numerical model. From experimental measurements the thermal conductivity value of the bentonite is 0.471–Sr·1.15SrWm–1 K–1, where Sr is the bentonite degree of saturation (volume of water/volume of pores).
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