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The ÚJV Řež, a. s. Integrity & Technical Engineering Division carries out the research of materials, e.g. their mechanical properties affected by irradiation, in order to ensure nuclear safety, prolong the lifetime of nuclear installations, and develop new materials for non-nuclear use.We carry out tests of the mechanical properties of irradiated and non-irradiated structural materials of NPP components.


  • Tests and research are carried out at the following workplaces:
    • Hot and semi-hot cells for the implementation of experiments and analyses on irradiated materials of NPP components. Under the supplementary surveillance programs for VVER-440 and VVER-1000 reactor pressure vessel steels, the specimen is currently under reconstitution by means of an electron beam which allows for significant quality improvement of information on irradiation impact on the mechanical properties of reactor steels.
    • Accredited laboratories for testing of mechanical properties of irradiated materials


  • Further, the ÚJV Řež, a. s. Integrity & Technical Engineering Division operates in the following areas:
    • Research and development of materials for operating nuclear reactors, low-power reactors, research reactors, and new generation reactors:
      • Implementation of experiments under surveillance programs of nuclear power plants – testing of mechanical properties of irradiated materials, including determination of the impact of interaction with the environment (e.g. autoclave testing);
      • Testing of mechanical properties of advanced materials for generation IV reactors (e.g. ODS steels, Ni alloys);
    • Testing of the impact of the environment, irradiation, and different types of load on material life;
    • Ageing simulation of weld joint materials and evaluation of related changes of mechanical properties;
    • Research in the field of fuel cladding materials.