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Reactive power compensation of electrothermal devices
Tomeš, Martin ; Paar, Martin (referee) ; Lázničková, Ilona (advisor)
The work deals with reactive-power compensation (power factor correction = PFC) in practice. The theoretical part describes the basic concepts of power factor correction, reasons for the PFC, and the ways of the PFC, eventually a sanction for a breach of rated power factor. Attention is given to basic partition of the PFC and compensation devices which are capacitors and detuning reactors. The practical part is focused on the PFC analysis for a concrete customer where the central compensation is projected. The practical part is also focused on a detuned power factor correction which is often used by reason of increases in number of nonlinear loads nowadays.
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Converter for DC Welding
Siuda, Petr ; Vorel, Pavel (referee) ; Patočka, Miroslav (advisor)
This master´s thesis with the peripheral and structural design of power converter that will be used for DC welding. The drive itself is based on the principle of two single-acting permeable converters operating in counter strokes to a mutual load. The inverter operates at a frequency of 60kHz, and its output current can be controlled from 0 - 100A. Welder is equipped with a variable constant current or power adjustment. The device is powered from a single-phase 230V.
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Materials for IV. generation power plants
Hovorka, Martin ; Svoboda, Pavel (referee) ; Šnajdárek, Ladislav (advisor)
The aim of this thesis is to describe material needs of chosen Generation IV nuclear reactors – VHTR, SCWR, and MSR with the emphasis on the VHTR. It describes the main principle and a constructional arrangement of VHTR components with its material demands. SCWR and MSR reactors are described in terms of its material requirements. The middle part of this thesis is dedicated to the available material candidate analysis. Main material properties are discussed and at the end of this part the suitability of chosen materials for a flange joint in VHTR heat exchanger is assessed. The last chapter (the practical part) is focused on an experimental proposal of changeability of older materials by the new ones using the electron beam welding method.
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Nuclear energy future development perspectives in the Czech Republic and in the world
Horák, Ondřej ; Lisá, Hana (referee) ; Milčák, Pavel (advisor)
The submitted bachelor's thesis deals with the irreplaceable role of nuclear energy and the types of reactors being designed at the same time. A large part of the work is focused on a relevant overview of nuclear reactors in the world, including those under construction. The thesis deals with the legislation of the Czech Republic in the field of nuclear safety and international cooperation between operators of nuclear power plants. In the conclusion of the bachelor's thesis, the perspective of the future development of nuclear energy in our country and in the world is mentioned. The research-synthetic method was used for processing the text.
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Evaluation of introduction protection measures - evacuation at crash of nuclear power station Fukushima
SLÁMA, Filip
The aim of this bachelor thesis is to evaluate the protective measures, notably the evacuation of the population, its development and progress. To achieve the goal of bachelor's work was determined by the research question: Was the safeguard measures and the subsequent procedure for the evacuation of persons from the evacuation zones sufficient? The theoretical part is focused on the particular issue of nuclear power plants, radiation protection and evacuation. The situation described here, which took place directly on the Fukushima daiichi nuclear power plant Daiichi, from the strike of the earthquake and tsunami, after the gradation events in the individual reactors. The research part is about the development of the evacuation in the evacuation zones and the nuclear power plant. Protective measures are described here, and even the consequences and the situation after the crash to the present. The methodology of this work was the gathering of available information from official foreign sources, legislative documents, but also of the publications of the experts. Processing of the available information and the evaluation of the consequences of the evacuation has brought unpleasant findings. The loss of life, which can make a person look a certain way to reflect over the selection of persons suitable to evacuate. In this work were identified and discussed technical shortcomings of the power plant, the information misconduct in communication of the population and in the last row and misconduct of the human factor. The thesis can be used in the general issue of nuclear power plants and evacuation for study purposes or as an information source in the education, energy or public administration.
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Emergencies in nuclear power plants
Šupík, Ondřej ; Fiala, Miloš (advisor) ; Vilášek, Josef (referee)
Title: Emergencies in nuclear power plants Objectives: The aim of this work is to summarize information about emergency plans of nuclear power plants Temelín, Dukovany and the accident at the Chernobyl nuclear power plant. Methods: Descriptive-analytical methods are used as methods in this work. Study sources and their subsequent research were used to develop this work. Results: The result is a summary of information on the emergency plans of the Temelín and Dukovany nuclear power plants and on the accident was the largest nuclear power plant accident in history. The current nuclear power plants in the Czech Republic place great emphasis on the prevention of nuclear accidents and on the overall safety of operation. Keywords: analysis, event, power station, reactor, measure
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Prototyp detektoru reaktorových antineutrin
Fajt, Lukáš ; Štekl, Ivan (advisor) ; Dragoun, Otokar (referee)
Title: Prototype of detector for detection of reactor's antineutrinos Author: Lukáš Fajt Department: Institute of Particle and Nuclear Physics Supervisor: Doc. Ing. Ivan Štekl, CSc., IEAP, CTU in Prague Abstract: This master thesis is related to the development of the complex detector of reac- tor's antineutrinos, so called S3 , which is based on the polystyrene scintillation detectors. The detector S3 (dimensions 40 x 40 x 40 cm3 ) will be located in the close vicinity of a nuclear reactor (5-12 m) and its purpose will be to measure reactor's power, isotopic composition of the nuclear fuel and moreover verification of the sterile neutrino hypothesis by detecting reactor's antineutrinos via the Inverse Beta Decay (IBD) interaction. Within the thesis, the first prototype of the antineutrino detector was constructed. It is composed of 18 scintillation plates (40 x 20 x 1 cm3 ) and corresponding electronics. With this prototype the first test with cosmic muons were performed. Within the thesis, the energy reso- lution of the scintillation plates was significantly improved by the optimization of their chemical composition and selection of the optimal refractive material. The proper energy resolution is very important for the detector functionality. In addition, a new methods for the production of coating layer...
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Temperature measurement in reactor VVER 440
Virgl, Martin ; Katovský, Karel (referee) ; Povalač, Aleš (advisor)
The main goal of this work is to get acquainted with the issues of temperature measurement and signal digitization in the theoretical level and temperature measurement in the VVER 440 reactor and on inseparable parts of the main circulation loops of the Dukovany Nuclear Power Plant and signal processing of temperature sensors. The measurement of temperatures in the power plant reactor is focused mainly on the used temperature sensors, A / D converters and a description of the systems processing these outputs. Furthermore, the work analyzes the data obtained during the calibration of temperature sensors in the isothermal state and the measurement of the resistance thermometer and thermocouple in laboratory conditions.
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Emergencies in nuclear power plants
Šupík, Ondřej ; Fiala, Miloš (advisor) ; Vilášek, Josef (referee)
Title: Emergencies in nuclear power plants Objectives: The aim of this work is to summarize information about emergency plans of nuclear power plants Temelín, Dukovany and the accident at the Chernobyl nuclear power plant. Methods: Descriptive-analytical methods are used as methods in this work. Study sources and their subsequent research were used to develop this work. Results: The result is a summary of information on the emergency plans of the Temelín and Dukovany nuclear power plants and on the accident was the largest nuclear power plant accident in history. The current nuclear power plants in the Czech Republic place great emphasis on the prevention of nuclear accidents and on the overall safety of operation. Keywords: analysis, event, power station, reactor, measure
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