Computational Tools and Models for Deterministic Safety Analyses

The project No. CZ.01.1.02/0.0.0/18_215/0016493 has been carried out in cooperation between the Faculty of Mechanical Engineering at the University of West Bohemia and TES. The project was focused on the development of CFD model presenting downcomer of the VVER-440/213 pressure vessel including the cold leg. The model enables to analyze the events which may endanger reactor pressure vessel integrity by the physical phenomena called “cold stripe”. The results should also facilitate obtaining the reference data for innovation and validation of computational models of the programs and methodologies for safety analyses performance using RELAP5 and TRACE computer codes. The project was co-financed by European Union under the Operational Programme for Enterprise and Innovations for Competitiveness.

In September 2018 the innovation project no. CZ.01.1.02/0.0/0.0/15_013/0004603 “Transfer of Knowledge in the Field of Neutronic-Physical Calculations for Safety Analyses of Nuclear Power Plants” was successfully finished. The project was realised between 2016 – 2018 under the Operational program Enterprise and Innovations for Competitiveness (OPPIK in Czech) as transfer of knowledge from the Faculty of Electrical Engineering and Communication of the University of Technology in Brno (FEKT VUT) to the applicant company TES s.r.o. that has been involved in the conduct of thermo-hydraulic and safety calculations of nuclear installations. The project was co-financed by the European Union.

The project has been chosen by the Ministry of Industry and Trade of the Czech Republic as one with the highest potential and quality that could be used as an example of good practice for coming projects.
The transfer accelerated and innovative process through development and validation of calculation models, programs and methodology facilitating the performance of advanced combined thermo-hydraulic and neutron-physical calculations of the  VVER and PWR nuclear power units in TRACE-PARCS and SCALE-TRITON computational programmes.

The project No. CZ.01.1.02/0.0/0.0/17_102/0011478 will be carried out in cooperation between the Faculty of Electrical Engineering and Communication of the University of Technology in Brno (FEKT VUT) and TES. In the frame of the project, codes, correlations and methodologies which are necessary for the calculation of critical heat flux in safety analyses of nuclear power units will be introduced/developed and validated. The project is co-financed by European Union under the Operational Programme for Enterprise and Innovations for Competitiveness.

The project aimed at analyzing of current system of all information support processes and optimising the future system. The project facilitated set up of a young team of experts allowing transfer of knowledge.

Research of the flow inside the reactor pressure vessel based on the outputs from the experimental measurements and key thermohydraulic effect analysis by CFD codes. The research enabled to develop strategies, procedures and methods for safe and effective reactor cooldown under accident conditions. The main aim of the project was to enhance the operating safety of the unit, reduction of the radiation risk during the potential accident, development and upgrading of the system thermohydraulic codes for NPP.