Abstract
The disposal container with low and intermediate level radioactive waste (LILW) was developed using self-consolidating concrete (SCC), which provides long term mechanical properties and extremely low permeability for liquids. In the paper, some results of additional investigations are presented, which complement the assessment of the behaviour of SCC during use. The main focus is the presentation and discussion of the results of SFR-SCC (steel fibre reinforced - self-consolidating concrete) tests in fresh and harden state. From these results it can be seen that there is a possibility of further improving the properties of the SCC and thus the container.
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