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The storage of highly radioactive waste from nuclear power plants is currently planned to be solved in the Czech Republic by the construction of a deep repository with a multibarrier concept. The key component of one of the barriers is bentonite, whose sealing properties will help to ensure optimal conditions for the disposal of radioactive waste. The focus of the thesis is on a review of the knowledge on the mechanical properties of bentonite and their change after exposure to high temperatures. The review is complemented by the current knowledge of the czech bentonite BCV from the Černý Vrch locality, which is also the material for the laboratory measurements carried out in this thesis. The key part of the work consists of laboratory tests, necessary for experimental verification of the discussed bentonite properties. Internally developed multipurpose cells (MPC cells) were used for the majority of the laboratory tests, as the standard equipment of soil mechanics laboratories has relatively little application for bentonite barrier research. The aim of the experimental part was to investigate how the swelling capacity and hydraulic conductivity of the material change due to previous thermal loading. The main objective of the work is to obtain an overview of the behaviour of the Czech Ca-Mg...