Aktivní a pasivní bezpečnostní systémy jaderného bloku EPR Areva
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Vysoká škola báňská – Technická univerzita Ostrava
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The bachelor thesis deals with the analysis of individual active and passive safety systems of the EPR Areva nuclear unit. To introduce the issue, the thesis first mentions the development of nuclear power plants and a description of the generation III+ of nuclear power units, as the EPR nuclear power plant counts among them. Furthermore, the thesis deals with individual active and passive safety systems of the nuclear unit EPR Areva and their arrangement into the safety sections. The thesis ends with the calculation portion focused on the thermal calculation of the vertical steam generator.
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nuclear power plant, EPR, safety system, generation III+, steam generator