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Provisions for mitigation of consequences in case of major accidents in GFR nuclear reactors
Mlčúch, Adam ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis deals with the severe accident of the gas-cooled fast reactor GFR. At the beginning of the study there is a review of the gas-cooled fast reactor subject. Next part is focused on description of possible solutions for severe accidents with emphasis on the solution applied in the Generation III+ reactors. Chapters that deal with material and thermal balance with severe accident of GFR demonstration unit, along with the chapter which analyses features of the corium, create a basis for the conceptual design of core catcher of GFR demonstration unit, which forms the final part of this thesis.
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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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Concept of a small nuclear reactor for the heat supply purposes
Bobčík, Marek ; Skála, Zdeněk (referee) ; Martinec, Jiří (advisor)
The objective of this diploma thesis is to assess the suitability of a small nuclear reactor for the purpose of heat supply in small towns and cities. First, all the heat demands of these towns and cities are analysed. Then, a small nuclear reactor to serve these needs is designed and a computational model for burn-up fuel is created. The thesis aims to propose a design of a new heat exchanger. Economic and environmental criteria are taken into account as well and including safety measures. The outcome of this thesis is an evaluation of the whole concept with respect to potential future implementation.
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Effect of a nuclear power plant in terms of radiatin burden
Vániš, Jiří ; Procházka, Zdeněk (referee) ; Belatka, Martin (advisor)
This text deals with ionizing radiation affecting nuclear power plant personnel and surrounding population. Irradiation limits of radiological industry personnel are also mentioned along with ways of protecting them and checks on absorbed ionizing radiation dose. In conclusion, a nuclear power plant, as a source of ionizing radiation, and its effects on contamination of water sources and gas vents are evaluated. The next part be engaged problematical of storage nuclear waste from the time, when is removed the nuclear waste from nuclear reactor, trough permanent storage.
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The 4th generation of nuclear reactors
Mlčúch, Adam ; Šnajdárek, Ladislav (referee) ; Nerud, Pavel (advisor)
This thesis reviews the particular generations of nuclear reactors. The biggest part of the thesis focuses on the projects of the fourth generation reactors. The individual projects come out from the analysis of the international forum GIF. The last part is devoted to the detailed description of VHTR system and demonstration plant concept with reactor Antares.
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The 4th generation of nuclear reactors
Katzer, Milan ; Škvařil, Jan (referee) ; Nerud, Pavel (advisor)
My thesis reviews the particular generations of nuclear reactors. The greatest part of the thesis focuses on the groundbreaking projects of the IV.generation reactors, which should be put into operation in 2030 or later. The individual projects come out from the analysis of the international forum GIF where six revolutionary nuclear reactors were chosen. The last chapter is devoted to the detailed description of one of the chosen reactors and its possible installation in the Czech Republic.
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Project of nuclear power unit secure emergency power supply for design basis accident as well as for extension conditions
Žák, Tomáš ; Šťastný, Jiří (referee) ; Katovský, Karel (advisor)
The present Master´s thesis aims at designing an evolutionary scheme of secured power supply at nuclear power plants with VVER 440 reactors during design basis accidents as well as design extension conditions. In the first part of this thesis, concepts relating to the defence in depth of nuclear reactors, operating modes of the blocks as well as types and possibilities of electrical power supply and electric circuits of the block are defined. Although the present thesis deals with PWR 440 in general, special emphasis is put on the Czech NPP in Dukovany, where there are four PWR 440 reactors in operation, and on the possibilities for enhancing the defence in depth in this area. The second part of the thesis deals with the difference in station blackout definitions before and after Fukushima; not only the differences in situation evaluation are dealt with, but a solution is also proposed to make the system of secured power supply system during design basis accidents as well as design extension conditions more robust. This option has been selected out of a number of possibilities based on the evaluation of reliability, availability and cost-effectiveness of the proposal.
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Review of world nuclear reactors
Blažková, Eva ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor work is focused on creating an overview of nuclear reactor types, their categorization and engineering approach to particular designs. Furthermore, it also lists countries having nuclear reactors in possession and their standpoint towards nuclear energy in general. A brief summary of the third and fourth generation and their future energy potential is included as well. This work primarily reflects present-day status.
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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.
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Severe accidents of third generation pressurized water reactors
Nečas, Karel ; Foral, Štěpán (referee) ; Černý, Tomáš (advisor)
The bachelor thesis focuses on the development of global nuclear energy. It clearly describes the development and division of nuclear facilities used for electricity production. The theoretical part of the thesis describes the division of nuclear facilities according to the development generations, the types are discussed in terms of technology and principle of operation. The operating conditions of nuclear reactors are described in detail, with emphasis on emergency conditions. The next part of the thesis focuses on the LOCA accident type for third generation pressurized water reactors. This thesis also includes an analysis of different approaches od the computation codes used for modelling various conditions of the nuclear power plants. The practical part of the bachelor thesis describes nuclear reactor APR1400. It provides its elementary parameters. The calculation code MELCOR was used for modelling this type of the nuclear reactor. The sensitivity analysis of the severe accident was performed using selected parameters. This analysis describes the influence of these parameters on the hydrogen production, the process of damaging of the active zone, and the reactor vessel melting time.
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