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Modernization the Dukovany Nuclear Power Station
Kissler, Martin ; Martinec, Jiří (referee) ; Fiedler, Jan (advisor)
Thesis focuses on a detailed technical description of all important parts of secondary circuit in Dukovany power plant and its connection to other systems of power plant. In thesis are analyzed significant adjustments which have been made during the entire operation of power plant including in particular the actions associated with project called Utilization of project reserves of units EDU. In the main part of the thesis were carried out calculations of the power plant's power for states before and after the modernization and there is also analyzed the impact of individual changes on the whole power plant. These changes are with the entire secondary circuit drawn in the T-s diagram.
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Radiation damage of VVER-440 based Dukovany NPP reactor pressure vessel investigation
Říha, Tomáš ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Dukovany Unit No. 3. In general damage mechanisms of reactor steels are described and possibilities of monitoring of material degradation and its recovery used at NPP’s all over the world are mentioned as well. A practical part of the thesis is focused on interpretation of analyses carried out with the assistance of MOBY DICK code. The ground of these analyses is a neutron fluence value development on different locations of RPV for the whole life of operation up to 24th cycle. The analyses results are put into context with performed in-service inspections. The thesis follows up with neutron fluence computation for the future cycles containing new types of nuclear fuel up to 34th cycle. The outcome of practical part of the master‘s thesis is a comparison between new types of nuclear fuel with respect to radiation damage of RPV’s.
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Analysis of possibilities for use of III. and IV. generation of nuclear reactors for the Czech Republic
Gajdzica, Lukáš ; Kopřiva, Radek (referee) ; Kopřiva, Radek (referee) ; Matal, Oldřich (advisor)
The thesis deals with the analysis of possibilities for use of III. and IV. generation of nuclear reactors for the Czech Republic. Introduction deals with basic principles of nuclear energetics and fuel cycle which is closely associated with the issue and its development and application in practice will have a significant effect both for choice of future types of nuclear reactors of IV. generation and the matter of settlement with spent nuclear fuel. In other parts the thesis deals with the present state of nuclear energetics in the Czech Republic, compares concrete chosen types of nuclear power plants of III. generation and generally describes nuclear reactors and power plants of IV. generation. Final part of the work is focused on questions concerning the possibility of construction of new blocks of nuclear power plants in the Czech Republic and presents concrete recommendation from author´s point of view.
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Simulation of Accelerator Driven Nuclear Reactor for Spent Nuclear Fuel Transmutation
Jarchovský, Petr ; Ing. Antonín Krása, Ph.D., SCK.CEN Mol (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with usage of burn-up (spent) nuclear fuel in nuclear power plants of next generation – accelerator driven transmutation plants which is produced in current nuclear power plants. This system could significantly reduce the volume of dangerous long-lived radioisotopes and moreover they would be able to take advantage of its great energy potential due to fast neutron spectrum. In the introduction are listed basic knowledge and aspects of spent nuclear fuel along with its reprocessing and the possibility of further use while minimizing environmental impact. As another point detailed description of accelerator driven systems is described together with its basic components. In addition this search is followed by individual chronological enumeration of projects of global significance concerning their current development. Emphasis is placed on SAD and MYRRHA projects, which are used like base for calculations. This last, computational part, deals with the creation of the geometry of subcritical transmutation reactor driven by accelerator and subsequent evaluation which assembly is the most effective for transmutation and energy purposes along with changing of target, nuclear fuel and coolant/moderator.
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Nuclear reactor power detectors based on Cherenkov radiation measurement
Čejka, Lukáš ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
This work deals with the connection between the luminance of Cherenkov radiation in a nuclear reactor and his power. Cherenkov radiation arises when charged particle passing through the medium if their speed is higher than the phase velocity of light in that medium. In water moderated reactors, it is caused by secondary electrons produced by absorption of gamma rays. The measurement is done using the camera and software for photometric luminance measurements. Furthermore, there is mentioned the use of Cerenkov radiation detection to measure burnout of spent nuclear fuel. There are examples of usage of Cherenkov radiation detection to measure of nuclear reactors power, including an analysis of the measured results on research nuclear reactor VR -1. The measured results show increasing intensity of Cherenkov radiation with increasing reactor power, but residual detection response caused by delayed gamma radiation was observed after the rapid decrease of the reactor power. Possible use of detection luminance of Cherenkov radiation is in monitoring unforeseen increase in reactor power or in the control of used fuel.
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Equipment for the enrichment of nuclear fuel
Ostrezi, Matěj ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
The aim of this bachelor thesis is to review the current knowledge and possibilities dealing with an enrichment of the nuclear fuel and to describe particular methods of the enrichment. An attention is paid to basic principles, functions, technological and power requirements and efficiency of the discussed methods. In conclusion, a difficulty of the enrichment process is pointed out and a balance sheet of the economic impact is made.
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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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Fuel of nuclear reactors and fuel cycle
Bátěk, David ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor thesis describes nuclear fuels used in today's nuclear reactors as well as parts of fuel cycle, which includes all activities like uranium mining and prepairing, energy utilization and storage at the end of a cycle. There are also information about world production of uranium and posibilities of manipulation with used nuclear fuel, including transmutation technologies.
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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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