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Turbochargers for internal combustion engines.
Holík, Petr ; Martinec, Jiří (referee) ; Škorpík, Jiří (advisor)
This bachelor thesis deals with theme of turbochargers for internal combustion engines and shows basic systematic view of this theme. The work is divided into three main chapters. The first chapter deals with historical development and usage of turbochargers. The second chapter attends to working principle and energy transformation in the turbochargers. In the third chapter there are mentioned main types of turbochargers and their parameters and worldwide producers.
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Pressure vessels pressurized water reactors
Horváth, Radovan ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
The aim of this bachelor thesis is the development of research on the topic of the pressure vessels of pressurized water reactors. Next is to outline the various design solutions of pressure vessels of pressurized water reactor. The thesis is divided into five chapters, contains 1 chart and 7 graphics. The theoretical part is dedicated to the history of nuclear energy and the development itself in the world. The description of the classifications of nuclear reactors is also included in the theoretical part. Summary of the theoretical part consists of a detailed description of the pressure vessel and pressurized water reactor itself. Practical part of this thesis contains the design of 3D assembly model and its modification in the program Catia V5. The overall model is composed of a main assembly, namely the body of the reactor and sub-assemblies, which were gradually installed.
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Possibilities of the external cooling of a pressure vessel in case of the accident with active zone melting
Hanuš, Jan ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
The accident at the Fukushima Daiichi nuclear power plant has shown us that there may be situations where the applied technology will not be able to successfully cool the reactor core. These situations may occur when more elements such as supply of energy to power the pumps and diesel generators are destroyed for example by tsunami or earthquake, or other not expected natural disasters. The inability of the residual heat removal leads to the melting of core, relocation to the bottom of reactor pressure vessel (RPV) and failure of RPV. Result of this accident may be containment failure and leakage of fission products into the environment. One way to prevent this scenario may be a passive system called IVR (In-Vessel Retention) by using external cooling of RPV that retains melted core in. This system counts with flooding of RPV´s shaft by water. After natural circulation of water provides the heat transfers from the wall of RPV. The applicability of IVR for VVER 1000 reactors is still in the course of research. However it´s already clear that the submersion of RPV shaft by water will not sufficient. Other elements as suitable insulation and RPV coating which provides a more intensive heat transfer from the walls of RPV will be needed.
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Fuel element characterization
Halabuk, Dávid ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This bachelor thesis describes the fuel rods of VVER reactors. In addition to general description of fuel rod, there is also overview of the nuclear fuel used in the past and at present in Czech and Slovak nuclear power plants, as well as overview of the new trends in development of nuclear fuel. Big part of the thesis is focused on description of nuclear fuel and fuel cladding properties and the individual processes affecting fuel rod during fuel burnup. Next part describes in detail the causes of fuel failures occurring in VVER reactors. The last part of the thesis includes calculation of changes of deformations and stresses occurred in fuel cladding during pellet-cladding interaction. Calculation is done for four different shapes of fuel pellets and in addition to deformation and stress analysis, there are also calculated axial dilatations of fuel column and radial temperature distributions in fuel rod.
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Effectiveness Evaluation of Waste-to-energy process
Klimek, Petr ; Martinec, Jiří (referee) ; Pavlas, Martin (advisor)
This diploma thesis is focused on the evaluation of the effectiveness of using municipal waste to produce energy. On the basis of legislation applicable in the EU methodology is summarized evaluation of the facility as an energy recovery of waste. In the thesis is also created a consecution to determine decisive coefficients of legislatively-based criteria. The consecution is applied to the case study. Thesis serves as the basis for a software application.
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Production of compressed air in the TZ Trinec
Kohut, Vojtěch ; Martinec, Jiří (referee) ; Fiedler, Jan (advisor)
The main purpose of this master’s thesis is description of the current technology of compressed air production in the grounds of Třinecké Železárny, a.s. (TZ). Compressed air for companies in the TZ area is manufactured and distributed by company Energetika Třinec, a.s. (ET). The part of the thesis is the preparation and execution of measurement including evaluation of specific energy consumption for production of compressed air by compressors of ET company. In conclusion there is proposed the possibility of substitution of compressors including the economic evaluation.
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Increasing the flow of cooling water for absorption cooling systems in the nuclear power plant Dukovany
Dvořák, Josef ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
The thesis focuses on comparison of the original and the new solutions of cooling water circuit of the York cooling units for the purpose of cooling water flow increase for the absorption units in the Dukovany Nuclear Power Plant. The individual parts of the cooling units that were changed and modified within a reconstruction are described here. The aim of the work is also to process and compare the original and the new solutions of the cooling units and the cold source station from the available measured data. The data are processed into illustrative graphs and tables. Based on the obtained data we can observe the changes achieved by the reconstruction that have affected the effectiveness of the cooling units.
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Experiments critical heat flux
Štaffa, Petr ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
The Bachelor’s thesis deals with phenomenon of critical heat flux in a core of nuclear reactor. The first part is dedicated to describe physical nature of critical heat flux and basic thermo mechanical and hydrodynamics terms. The second part is dedicated to summarize experimental investigations on critical heat flux and their process.
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Tightness measurement of hermetic compartments in NPP
Sklenár, Ondrej ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This diploma thesis deals with measuring the tightness of the hermetic area of nuclear power plant in the way of improving safety. Describes the layout and function of this area - the primary circuit of NPP with WWER 440/213 reactors, as well as methodology for leakage search and leakage calculation procedures. Personal contribution to the issue is a proposal improving tightness of the current state in hermetic area of NPP Jaslovské Bohunice – transition of jacketed pipe designed to collect water from the floor in the box of the steam generator to the heat exchanger of the shower system. This system belongs to the safety system designed to reduce pressure in the LOCA type of accident.
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Steam turbine
Šamalík, Jakub ; Martinec, Jiří (referee) ; Fiedler, Jan (advisor)
In this master’s thesis, I made a thermodynamic calculation of a steam turbine under the parameters given. In order to increase the efficiency of the low-pressure turbine section and to reduce axial length of the low-pressure rotor, a radial stage is designed in this section. The master’s thesis also includes a design of the low-pressure section. The thesis is divided into chapters, which contains a calculation of the single sections of the turbine. In the introductory chapters, the single sections of the turbine engineered are theoretically discussed. In the conclusion, assessments of the benefits of the use of radial stage are made.
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