|
|
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.
|
|
|
FACTORS LIMITING LIFE TIME OF NUCLEAR POWER PLANTS WITH PRESSURIZED-WATER REACTORS
Křivánek, Robert ; Kolat, Pavel (referee) ; Liszka, Ervin (referee) ; Fiedler, Jan (advisor)
The aim of the thesis is to analyze the state of preparedness of nuclear power plants (NPP) for long term operation (LTO) based on the IAEA SALTO (Safety Aspects of Long Term Operation) peer review service, analysis of the most significant failures, accidents and operational experience with type reactors PWR/VVER focusing on cases caused by equipment ageing and identification of major structures and components limiting life time of PWR/VVER-type nuclear power plants, and possible measures to ensure their required service life. Based on the results of the IAEA SALTO peer review service, an analysis of the main deficiencies and measures of NPPs in preparation for a safe LTO was performed, focusing on topics whose deeper knowledge is important for the future more precise determination of technical factors limiting the lifetime of NPPs. The main deficiencies and measures in the preparatory phase for LTO and the most important technical measures are summarized in chapter 4.5. The main deficiencies and the most important technical corrective measures in the area of ageing management of structures and components are discussed separately. The history of major failures and operational experience of nuclear power plants with PWR/VVER reactors from the point of view of ageing of structures and components is analyzed in chapter 6.2. The result is a statistic analysis of ageing-related events, an overview of the most significant PWR/VVER reactor failures with an impact on their service life, a statistical overview and discussion of the most important degradation mechanisms, and other important findings from the history of major failures and operational experience. Chapter 6.3 analyzes factors limiting the operation of nuclear power plants with PWR/VVER reactors with focus on structures and components potentially limiting the life of PWR/VVER reactors and possible measures to ensure their required life. In conclusion, the main reasons of permanent shut down of NPPs (actual and potential) for 40, 60 and 80 years of operation and the measures to ensure their required life are summarized.
|
|
|
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.
|
|
|
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.
|
|
|
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.
|
|
|
Orbital welding in terms of nuclear power plant Temelin
Toman, Petr ; Šnajdárek, Ladislav (referee) ; Fiedler, Jan (advisor)
The bachelor thesis deals with the selection of a suitable system for Orbital welding of impulse pipe at the Temelín Nuclear Power Plant. The aim of this work is to describe the current TIG method of manual welding, to describe the available Orbital welding technology, to select a suitable type of kit and to design an experiment to compare the products of individual manufacturers.
|
|
|
The concept for passive cooling of the VVER-1000 reactor
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis is focused on the design of passive cooling system for a nuclear reactor VVER- 1000.This type of reactor is located in the Czech Republic in the location of Nuclear power plant Temelín. The thesis states an overview of the different cooling systems of nuclear power plants. The thesis is focused on passive safety system especially on passive cooling system, so there was done an overview of currently used passive safety system. In the work is discussed nuclear safety and the maximum projected accident of VVER-1000, which is called LOCA accident. In the design part of the thesis was done thermal calculation of heat exchangers. Exchangers are designed as condensers with a natural flow, where cooling of system is provided by outside airflow in case an accident. The results are evaluated at the end of the thesis.
|
|
| |
|
|
The Nuclear Power Plant – The Green Source of Energy
Hynčica, Martin ; Vágner, Jiří (referee) ; Vágner, Jiří (referee) ; Matal, Oldřich (advisor)
This diploma thesis deals with nuclear energetics and its impact to the environment. Present state of the energetics, mainly nuclear energetics, in the Czech Republic is discussed here. Also perspective of nuclear energetics is given. The thesis describes nuclear power plant waste handling and also spent nuclear fuel handling. Nuclear power plant is compared with other sources of electric energy, which are counted to the energetic mix. The author focuses on fossil fuels and also on the renewable energy sources. The amount of produced waste to the unit of produced energy, built up area, safety and economic indicators and other parameters are followed for each source of energy.
|
|
|
Role of Czech NPP within grid power regulation
Kostečka, Jan ; Martinec, Jiří (referee) ; Katovský, Karel (advisor)
The aim of the Bachelor’s thesis is the involvement of Czech nuclear power plants in the Czech energy networks, but also in the European Network and their adaptation. Effect of expansion of renewable electrical energy produces the asymmetry in the network and places formed with an excess of electrical energy and places with lack of electrical energy. Flows of electric energy can affect the security and safety of distribution lines. Excessive overloading can cause them to collapse. Therefore, this work is focused on solutions and avoids this problem and minimizes this potential damage. However, the impact of energy revolution has a giant proportion about these overflows network energy. Uncontrollable wind and solar power source may create regionally region surge and flow of this energy goes to areas with shortages of electrical power. The regulation has an impact on fuel. This renegade production could extend fuel cycle, or expand the campaign to more years at least a year. The calculations can show the amount of fuel that can still be used, and thereby increase the yield and economic benefit conditions for extending the life of the reactor units.
|
guest ::
