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Evaluation of power and coolant flow in reactor core
Tvrdý, Miloslav ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
This graduation thesis deals with evaluation of power and coolant flow in reactor core. The first part is a description of nuclear power plant VVER 440. It is focused on parts important for transfer and utilize energy in regular operating of generating block. In the second part, the equations for calculation of power and coolant flow in reactor core are deduced. The last part is about designing the program for calculation of published values. There are specified requirements for the program and on the basis of this the source code is written. The parts of code are described. In conclusion of this part, the user's manual is work out. The program is on CD in the annexe.
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Parking house of NPP Dukovany
Okounová, Kateřina ; Rosendorf, Aleš (referee) ; Boleslavská, Yvona (advisor) ; Matějka, Libor (advisor)
The theme of this thesis is the design of two parking houses, which will be made in stages in the area of the Dukovany nuclear power plant. The construction site is located directly in the Dukovany NPP site, south of the cooling towers, which do not interfere with the area in any way. North of this area is a commercial area and bus station, which is separated from the land by buildings and greenery. The five-storey parking houses will not disturb the surrounding character of the buildings. Cooling towers have a big influence on this and they are unmistakable by their height and the designed objects will not have a massive effect next to these towers, they only complement the surrounding buildings. The buildings are designed of regular shape. A more prominent feature on these buildings will be the front facade itself and the glass staircase spaces. The main entrances to the building will be marked with a light sign “P1” and “P2” for better orientation between buildings. The layout of the parking house "S01" in the first stage is designed using two ramps located in the middle of the building. There is also a station for charging electric cars, bicycle storage, sanitary facilities, cleaning room and TZB room. The stairwells are designed in three places for easier access of people. The parking function is complemented in the 1st floor with 6 self-service car wash boxes, which are only accessible from outside the building due to the wet use process. The second stage of construction is considered to be the same layout, the entrance to the second building "S02" is designed from the west side.
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Design of a heat exchanger in a nuclear power plant
Kocanda, Tomáš ; Kudela, Libor (referee) ; Milčák, Pavel (advisor)
This bachelor thesis focuses on the design of heat exchange in nuclear power plant, more specifically on low-pressure heater 2. The introduction of bachelor´s thesis deals with the introduction of nuclear energy and nuclear power plants. The following chapters describe low-pressure regeneration as well as low-pressure heater. In the last part of the work, the heater is calculated from the entered values and values subtracted from the overall thermal scheme of the secondary circuit of the Dukovany nuclear power plant.
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Conceptual design of secondary and tertiary circuit for a new nuclear source
Valíček, Roman ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The aim of this thesis is to create a conceptual design of the secondary and tertiary circuit of a new nuclear power plant in our country, which is preceded by a brief search of particular generations of nuclear reactors. The VVER-1200 reactor became the model for the new nuclear power plant. There was designed a heat diagram containing primary components in this work. After that, there was the balance calculation and calculation of parameters of the main devices of the proposed scheme such as condenser, low-pressure and high-pressure regeneration exchangers and steam generator.
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Grid Node Operation after Large Nuclear Unit Connection to the Grid
Prokop, Ondřej ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
The thesis deals with the analysis of the grid node operation after the connection the nuclear unit. The aim of the master´s thesis is to describe the influence of network´s faults to a nuclear unit. Thesis is dealing with three fundamental problems. An influence of short circuits and power imbalance on the synchronous generator of nuclear power plant and its operation of the island network. The thesis is focused especially on the nuclear unit. However, in the case of any failure in the network, it´s necessary to check other units and their protections in the test system because unit failure could cause the disintegration of the power network. For the purposes of the simulation a test system of the power network has been developed. The test system was optimized in the LUG software, which is used to calculate the power network. Transient simulations are performed in the MODES software. Single faults are configured with scenarios. Results are generated into output files. Analysis of influence network´s faults on the synchronous generator of nuclear power plants. The ability of the synchronous generator to restore the primary steady state or hold the new steady state during changes in operating parameters of the network is one of the important parts of the safe and reliable operation of the power network. During the short circuit the damped transient actions occur. With the extension of the short circuit duration, the amplitude of the transient action increases. The risk of the stability loss of a synchronous generator increases. Therefore, the critical clearing time of a short circuit is being defined, which is the time when there is not any loss of stability. Critical clearing time of research generator is sufficient to turn off the short circuit with the help of its protection (the worst case is 0,8 s). For example, by comparison with the hydroelectric power plant, the critical clearing time is much longer. Models of other power plants have been designed with high reliability so in the case of these faults, it doesn’t cause the disintegration of the power network. Creation of island grid is characterized by strong current surges. Units must be resistant to these surges. In the island grid fast changes of the electrical parameters often occurs. Therefore, units must respond to these changes as quickly as possible and in the broadest limits. For this purpose an island operation regulator is being used. In the case of surplus island grid in steam power plants a dump condenser can be used. This is an important ability of steam power plants because the units are able to react quickly to changes of electrical parameters in island grid. The main result of this thesis is the behavior of the nuclear power plant during various faults in the power network. Researched generator of the nuclear power plant is highly stable against faults in the power network based on the findings. The results allow to continue in this topic with real network and real unit of nuclear power plant.
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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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Possibilities of nuclear energy in the field of energy and media production
Svoboda, Filip ; Lisý, Martin (referee) ; Milčák, Pavel (advisor)
The main objective of this thesis is the possibility of combining nuclear power plants with energy storage technologies (specifically hydrogen production) and the subsequent balance of electricity and hydrogen production when combining these hybrid systems with photovoltaic power plants. With large installed capacities of renewable energy sources, it is necessary that other sources in the energy portfolio are flexible and then it is possible to regulate the supply of electricity from these sources to the electricity grid (for example, reducing the output of a steam power plant for natural gas on sunny and windy days). The regulation of a nuclear power plant is limited and therefore it is advantageous to start using it, for example, in a hybrid system with a PEM electrolyser. Then the nuclear power plant can produce electricity at a constant rate and only regulate the amount of electricity that goes to the grid or to the electrolyser.
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Condenser design of a nuclear power plant
Hejduk, Michal ; Šnajdárek, Ladislav (referee) ; Milčák, Pavel (advisor)
The topic of this master´s thesis is the design of the steam generator for a nuclear power plant with VVER 440 reactor. The first part of this thesis describes a brief history of nuclear research, which is followed by an overview of nuclear reactors used now. The next part deals the types of steam the types of steam generators used today with their basic elements and design recommendations. The last and final part is the design of a steam generator for nuclear power plant with a VVER 440 reactor. Above all, is the thermal calculation of the steam generator and behaviour of steam generator depending on the reactor power. The design solution of steam generator and its strength calculation. The last part of the steam generator calculation the pressure loss of the steam generator is investigated.
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The analysis of laboratory X-ray device using possibilities and detection to ensure the entery into nuclear power plant.
Vlk, Petr ; Zeman, Miroslav (referee) ; Varmuža, Jan (advisor)
The thesis deals with the use of X-ray device for analysis of imported objects when entering a nuclear power plant. It describes the principles of X-ray generation and detection and techniques used in current X-ray devices. The thesis includes analysis of legislative requirements related to the safety of nuclear power plants and operation of X-ray devices. The benefit of the thesis is a proposed laboratory task using the Heimann HI-SCAN 6040-A X-ray device, which demonstrates detection and differentiation of analyzed objects and various types of materials. An integral part is the verification of the dose rate limits near the laboratory X-ray device, based on the knowledge of the legislative requirements.
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Thermodynamics of the steam cycle of nuclear power plants
Kozák, Tomáš ; Klimeš, Lubomír (referee) ; Štětina, Josef (advisor)
In the first part, the bachelor thesis is focused on derivation of relations that describe thermal cycles. Then, there is an analysis of the ideal Carnot cycle and the Rankine cycle. The ways of increasing the thermodynamic efficiency of Rankine cycle are mentioned, especially the ones that are focused on generating of electricity in nuclear power plants. The second part describes different types of nuclear reactors, their design, the cooling methods and the steam production. The development of the generation IV. nuclear reactors is mentioned at the end of the bachelor thesis.
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