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ÚJV Řež, a. s. carries out research and development activities for nuclear reactors in operation as well as for nuclear reactors of new generation and small nuclear reactors.


Work and tasks in connection with nuclear reactors offered and dealt with by ÚJV Řež, a. s. include a broad range of activities and analyses, supported by experience, knowledge, and obtained, or the self-created know-how of a broad and professionally varied spectrum of workers. This involves research reactors and nuclear reactors operating in the Czech Republic (VVER 440 and VVER 1000 types) or reactors whose construction is anticipated in the Czech Republic. We also focus on nuclear reactors of new generation as well as research-related newly preferred problems related to small nuclear reactors.

 

  • The research and development of reactors can be primarily divided into two areas:
    • The first area is support for existing nuclear power plants, i.e. support for the operation of reactors from the perspective of nuclear safety, radiation protection, emergency planning, more efficient operation, lifetime prolongation, etc.
    • The second area is the monitoring and preparation of development of nuclear reactors in order to make the "nuclear community" readily prepared, in compliance with the needs of the energy sector of the Czech Republic, and to significantly and responsibly contribute to the development of safe nuclear energy.

 

  • From the perspective of nuclear safety and reliability, the ÚJV Řež, a. s. Nuclear Safety and Reliability Division deals with and offers knowledge from the following areas:
    • Development and maintenance of safety assessment methods for nuclear reactor fuel charges;
    • Development of computation methods and tools for generation III and IV reactor core physics;
    • Development, validation and application of computation program methods for the needs of safety-related documentation for design basis and beyond design basis events of nuclear power plants;
    • Comprehensive analyses of thermomechanical behaviour of nuclear fuel in operating and emergency conditions;
    • Comprehensive analyses of the course of severe accidents of nuclear power plants and draft program for the management of severe accidents;
    • Use of advanced methods for diagnostics of components and equipment;
    • Reliability and risk analyses (in particular, PSA1 and PSA2 studies) including identification of weaknesses in the operation and design, draft modifications, and remedial measures.

 

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