|
|
Assessment of heat exchangers replacement
Kocanda, Tomáš ; Baláš, Marek (referee) ; Milčák, Pavel (advisor)
This thesis addresses the issue of heat dissipation from the oil system, specifically the lubricating oil of a diesel generator at a nuclear power plant. The literature review section introduces diesel generators, describes the heat exchangers used, and provides a detailed explanation of the problem in the context of a nuclear power plant. In the computational section, a verification calculation of the existing shell-and-tube oil cooler is first performed, followed by the design of a new plate heat exchanger according to specified parameters without altering the layout. In the final part of the thesis, an analysis of the new design compared to the existing one is conducted, including an evaluation of the layout.
|
|
|
Water Treatment in a Nuclear Power Plant
Hoskovec, Martin ; Kracík, Petr (referee) ; Chýlek, Radomír (advisor)
This thesis deals with the issue of water treatment for nuclear power plants. The aim of the work is to analyse in detail the processes and technologies used in water treatment, which is crucial for the safe and long operation of nuclear power plants. In the first part, the possibilities of water sources and what substances they contain are presented. In the following part, water pretreatment methods, water demineralization and other treatment technologies are presented. The third part of the thesis deals with reactor partitioning and their chemistry program. The next part describes the water treatment with chemistry program at the Temelin nuclear power plant. The last part of the thesis compares water treatment methods, their advantages, and disadvantages.
|
|
|
Technology of increasing the efficiency of nuclear power plants
Poláková, Barbora ; Imrichová, Anna (referee) ; Milčák, Pavel (advisor)
This bachelor thesis deals with increasing the efficiency of nuclear power plants, specifically the design of a steam heater. The introduction is devoted to nuclear energy in general, its history, the principle of energy extraction and new nuclear sources in the Czech Republic. The second part focuses on the analysis of the Dukovany nuclear power plant and the possibilities of increasing its efficiency. The third part describes in detail the steam separation and heating technology and its influence on efficiency. In the last two chapters is resented the thermodynamic analysis and the design of the heat exchanger, the aim of which was to determine its length and heat transfer surface.
|
|
|
Implementation of automatic controls of electrical signals for the monitoring system of the Temelín Nuclear Power Plant
Mareček, Michal ; Novotný, Pavel (referee) ; Drápela, Jiří (advisor)
This bachelor's thesis deals with individual electrical devices for self-consumption, focusing on production blocks of the nuclear power plant Temelín, which are continuously monitored by the superior electrical monitoring system NEMES. A key element is the description of the areas of power output and self-consumption of the electrical blocks of the power plant, including the NEMES system, necessary for the design of automatic checks of the measured electrical signals reliability. Knowledge of the device concept and operating modes is crucial to the successful implementation of NEMES system signal checks in logical links and in view of deviations from the band of operating values. The subject of the thesis is to propose limits for all main electrical equipment together with blocking conditions for performing automatic checks of the reliability of the monitored signals by the NEMES system, which will be of great benefit to the end user - the operator of the Temelín nuclear power plant.
|
|
|
Nuclear power plant cooling and condenser design
Caletka, Aleš ; Imrichová, Anna (referee) ; Milčák, Pavel (advisor)
The presented bachelor thesis deals with the thermal balance calculation of the cooling circuit of a nuclear power plant and the design of the basic dimensions of the condenser. For the computational part of the thesis, a nuclear power plant located in the Czech Republic was considered, utilizing a cooling tower with natural draft and a water-cooled condenser. The thermal calculation was based on the parameters of the external environment - temperature, pressure, and humidity, and the steam flow, which were used to determine the parameters necessary for the condenser design - cooling water flow rate, inlet and outlet temperature of the cooling water, and pressure in the condenser. The condenser design was considered with straight tubes of 22x0,5 dimensions. Thermal and pressure losses in the condenser were neglected in the calculation. The result of the design calculation was a length of one tube of 22,8 m and a total heat exchange surface area of 88 100,436 m2. Within the theoretical part of the thesis, the technology of cooling nuclear power plants was introduced, and possible technological solutions of cooling towers were discussed.
|
|
|
Design of the internal circuit of the system for long-term heat removal from NPP hermetic zone
Zemanová, Silvie ; Baláš, Marek (referee) ; Milčák, Pavel (advisor)
The diploma thesis deals with the safety of nuclear power plants and the design of a system for long-term heat removal from the hermetic envelope of the WWER 440 model 213 NPP intended for severe accident management. The thesis contains a description of the course of selected severe accidents and the causes of their occurrence and presents approaches (the concept of defence in depth) and measures (implementation of new systems) by which operators aim to prevent and prepare for their management. The practical part of the diploma thesis is devoted to the design of the piping route of the long-term heat removal system (dimensions, material, wall thickness, layout) and the calculation of the hydraulic losses of this route, it also deals with the conceptual design of the heat exchanger for the above-mentioned emergency system and its thermal calculation.
|
|
|
Design of the thermal output for district heating line from the Dukovany nuclear power plant
Houzar, Filip ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The topic of this master's thesis is the analysis and comparison of possible designs of thermal power output from the nuclear power plant Dukovany to meet the needs of the city of Brno. The beginning part of this thesis contains research on the current state of the heating industry in Brno, including current industrial heating sources and heat consumption. This research also includes a summary of the secondary circuit of the Dukovany NPP, from which the heat will be obtained. Three possible designs of heat output will be proposed in the next chapters, varying in the use of steam extracted from the steam turbine and the placement of heat exchangers. The last part of this thesis contains the basic design of a district heating pipeline necessary for the long-range transport of heat from Dukovany to Brno.
|
|
| |
|
|
Nuclear power plants and their safety
Novotný, Petr ; Köbölová, Klaudia (referee) ; Milčák, Pavel (advisor)
The bachelor thesis deals with the current state of nuclear energetics. It describes the development of nuclear power plants to date and specifically describes the most commonly used types of nuclear reactors. Most of the reactors currently in operation are second generation reactors. However, a number of third-generation reactors with improved technological and safety parameters are already under construction. Improved safety lies in the improvement of active safety systems, but also in the increased use of passive safety systems. The paper concludes with a comparison of specific solutions from the most important nuclear reactor manufacturers in the world.
|
|
|
Nuclear power plant condenser design
Havel, Jaroslav ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The submitted bachelor’s thesis deals with the design of a condenser for the new Dukovany II nuclear power plant with an electrical output of 1,200 MW. The specified condensation parameters reflect typical parameters of pressurized light-water moderated and cooled reactors of the same power and climatic conditions in the given location. From the assignment of the thesis and the research carried out, the following requirements for the designed device emerged: to ensure the condensation of steam in the secondary circuit in filmwise condensation mode, to comply with the maximum cooling water heating of 10 K, to install the tube bundle at optimum angle and to ensure the competitiveness of the product. For the selected concept with a four-body condenser, a thermal analysis was made and solved numerically by a fixed-point iteration method. The calculation was performed using the EES software. The results showed that a heat transfer surface area of 121,263.96 m is required to ensure failure-free operation of the condenser. Each condenser body consists of 31,400 titanium tubes with a cross-section of ( 22 × 0,5) mm and a length of 14,554 mm. A dimensional drawing is also attached.
|
guest ::
