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Trasfer Heat Analysis in Steam Generators in blocks of VVER 440
Roupec, Petr ; Pulec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to analyze the heat transfer in steam generator of blocks in the nuclear power plant VVER 440. The steam generator represents the border between the primary and the secondary circuit. The heat is carried from a warm water from reactor to a cold water. The steam arises after the heat transfer and drives the steam turbine. An important quantity which represents the heat transfer is a heat transfer factor. This thesis is divided into theoretical and a practical part. In the theoretical part is mentioned a principle of the steam generator and the theoretical calculation of the heat transfer factor, which comes first of all from the character of the streaming in the steam generator. The practical part brings a comparison of the heat transfer factor calculated from data measured after the start of the third block of EDU in 1986, with the heat transfer factor which comes from the measurement after the power-increase for 105 % of nominal power of the same block in 2009. Further is shown the prediction of the heat transfer factor for next power-increase and the following service is shown too.
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Design of the steam generator for modular reactor
Černý, Marian ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
Subject of this thesis is design of the steam generator for modular reactor. The dissertation consist of the theoretical part, where are described heat-exchangers and steam generators used in nuclear power plants. Second part contains theoretical calculations in the first approach (thermal, hydraulic and strenght calculation). In the next part are particular variants of steam generator selected. For the final variant are necessary calculations (introduced above) and drawings of selected parts are done. In the final statement is technical solution evaluated, and the parameters of the steam generator are compared with actually used steam generators.
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The heat dissipation efficiency of the steam generator Dukovany at low water levels
Veselý, Jakub ; Šnajdárek, Ladislav (referee) ; Pospíšil, Jiří (advisor)
The goal of this thesis is to simulate the course of events during Dukovany Nuclear Power Plant blackout and to determine the optimal process of cooling down the cold branches of the primary circuit loops to secure the maximum amount of the primary fuel needed for the residual heat outlet so that the operating staff has as much time as possible for renewing the electric power supply. The first part of the thesis describes nuclear power plants built in the Czech Republic and in the world as well as reactor blocks whose construction is being considered. The detailed description of Dukovany’s steam generator is shared in chapter three. Following chapter summarizes blackouts that occurred at power plants around the world, events that might have led to blackouts in the Czech Republic, and it also describes current approach to blackout problematics at Dukovany Nuclear Power Plant. Chapters six and seven contain the core of the thesis. That includes detailed description of a mathematical model explaining the behaviour of a reactor block during blackout as well as the analysis of the results found.
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Steam generator heated with liquid sodium
Kóša, Štefan ; Bogdálek, Jan (referee) ; Šen, Hugo (advisor)
This bachelor’s thesis is concerned with engeneering a steam generator (secondary heat exchanger) for a fast breeder reactor. It includes proposal of the projected type, thermal, hydraulic and strenght calculation, and examination of a proposal in light of nuclear safety. It contains a lay-out of selected parts.
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Calculation of Parameters of Secondary Circuit of Nuclear Power Plant
Vaněček, Lukáš ; Lázničková, Ilona (referee) ; Raček, Jiří (advisor)
The contents of this thesis is a suggestion of calculation and follow-up calculation of parameters of secondary circuit of assigned thermal diagram and parameters of a nuclear power plant. The thesis also includes possibilities of making nuclear circulations. Part one of the thesis briefly describes possibilities of making nuclear circulations, types of nuclear energy reactors, types of steam generators and types of turbines used in nuclear power plants. The second part of the thesis includes a suggestion of calculation for the real thermal diagram of secondary circuit of nuclear power plant. The attention in this calculation is given to expansion of steam in a turbine, determining parameters of mass in a circuit, calculation of steam demanded and determining power and efficiency of nuclear power plant. The final part of the thesis is a calculation of parameters of secondary circuit of nuclear power plant for given values and evaluation of results of calculation.
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The steam generator for ESFR reactor
Bátěk, David ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master thesis deals steam generator for ESFR (European Sodium Fast Reactor), which is heated by liquid sodium. In the beginning chapters, there are theoretic information about ESFR's parameters and its' comparison with ohter types of heat exchangers in nuclear reactors with the same principal (sodium as a coolant). Then designing part follows, which contents of introduction of calculations, option of material and conception of heater. Computational part on its own includes thermal, hydraulic and stress calculations and comparison with aspects in nuclear safety and security.
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Sodium steam generator for experimental stand
Janíček, Martin ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This thesis deals with the experimental liquid sodium heated steam generator. The first chapters describe the many aspects that should be taken into account when designing this type of steam generator. Furthermore, is approximated in the proposal the work itself. On the basis of thermal, hydraulic calculation of strength and was chosen one preferred option. In conclusion, the best option is evaluated steam generator sodium-water and the possibility of realization.
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Modernization the Dukovany Nuclear Power Station
Kissler, Martin ; Martinec, Jiří (referee) ; Fiedler, Jan (advisor)
Thesis focuses on a detailed technical description of all important parts of secondary circuit in Dukovany power plant and its connection to other systems of power plant. In thesis are analyzed significant adjustments which have been made during the entire operation of power plant including in particular the actions associated with project called Utilization of project reserves of units EDU. In the main part of the thesis were carried out calculations of the power plant's power for states before and after the modernization and there is also analyzed the impact of individual changes on the whole power plant. These changes are with the entire secondary circuit drawn in the T-s diagram.
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The heat dissipation efficiency of the steam generator Dukovany at low water levels
Veselý, Jakub ; Šnajdárek, Ladislav (referee) ; Pospíšil, Jiří (advisor)
The goal of this thesis is to simulate the course of events during Dukovany Nuclear Power Plant blackout and to determine the optimal process of cooling down the cold branches of the primary circuit loops to secure the maximum amount of the primary fuel needed for the residual heat outlet so that the operating staff has as much time as possible for renewing the electric power supply. The first part of the thesis describes nuclear power plants built in the Czech Republic and in the world as well as reactor blocks whose construction is being considered. The detailed description of Dukovany’s steam generator is shared in chapter three. Following chapter summarizes blackouts that occurred at power plants around the world, events that might have led to blackouts in the Czech Republic, and it also describes current approach to blackout problematics at Dukovany Nuclear Power Plant. Chapters six and seven contain the core of the thesis. That includes detailed description of a mathematical model explaining the behaviour of a reactor block during blackout as well as the analysis of the results found.
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Calculation of Parameters of Secondary Circuit of Nuclear Power Plant
Vaněček, Lukáš ; Lázničková, Ilona (referee) ; Raček, Jiří (advisor)
The contents of this thesis is a suggestion of calculation and follow-up calculation of parameters of secondary circuit of assigned thermal diagram and parameters of a nuclear power plant. The thesis also includes possibilities of making nuclear circulations. Part one of the thesis briefly describes possibilities of making nuclear circulations, types of nuclear energy reactors, types of steam generators and types of turbines used in nuclear power plants. The second part of the thesis includes a suggestion of calculation for the real thermal diagram of secondary circuit of nuclear power plant. The attention in this calculation is given to expansion of steam in a turbine, determining parameters of mass in a circuit, calculation of steam demanded and determining power and efficiency of nuclear power plant. The final part of the thesis is a calculation of parameters of secondary circuit of nuclear power plant for given values and evaluation of results of calculation.
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