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The concept for passive cooling of the VVER-1000 reactor
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis is focused on the design of passive cooling system for a nuclear reactor VVER- 1000.This type of reactor is located in the Czech Republic in the location of Nuclear power plant Temelín. The thesis states an overview of the different cooling systems of nuclear power plants. The thesis is focused on passive safety system especially on passive cooling system, so there was done an overview of currently used passive safety system. In the work is discussed nuclear safety and the maximum projected accident of VVER-1000, which is called LOCA accident. In the design part of the thesis was done thermal calculation of heat exchangers. Exchangers are designed as condensers with a natural flow, where cooling of system is provided by outside airflow in case an accident. The results are evaluated at the end of the thesis.
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The diverse system for heat transfer from the active zone
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This bachelor’s thesis is focused on diverse system for heat transfer from the active zone of the nuclear power plant Temelín. This result is output of stress tests. These stress tests were resulted as a necessary output from the nuclear accident at Fukushima - Daiichi, in order to improve nuclear safety. The outcomes of stress tests of nuclear power plants in Czech Republic are mentioned in next section of the thesis. Part of the safety systems of nuclear power plant Temelín is described in the next section. Next section is focused on the diverse system. In the end of the thesis is final energy balance between a steam generator and an amount of coolant in case that the diverse system for heat transfer from the active zone would be used.
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The concept for passive cooling of the VVER-1000 reactor
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis is focused on the design of passive cooling system for a nuclear reactor VVER- 1000.This type of reactor is located in the Czech Republic in the location of Nuclear power plant Temelín. The thesis states an overview of the different cooling systems of nuclear power plants. The thesis is focused on passive safety system especially on passive cooling system, so there was done an overview of currently used passive safety system. In the work is discussed nuclear safety and the maximum projected accident of VVER-1000, which is called LOCA accident. In the design part of the thesis was done thermal calculation of heat exchangers. Exchangers are designed as condensers with a natural flow, where cooling of system is provided by outside airflow in case an accident. The results are evaluated at the end of the thesis.
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The diverse system for heat transfer from the active zone
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This bachelor’s thesis is focused on diverse system for heat transfer from the active zone of the nuclear power plant Temelín. This result is output of stress tests. These stress tests were resulted as a necessary output from the nuclear accident at Fukushima - Daiichi, in order to improve nuclear safety. The outcomes of stress tests of nuclear power plants in Czech Republic are mentioned in next section of the thesis. Part of the safety systems of nuclear power plant Temelín is described in the next section. Next section is focused on the diverse system. In the end of the thesis is final energy balance between a steam generator and an amount of coolant in case that the diverse system for heat transfer from the active zone would be used.
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