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The state-of-of-art of research and design of nuclear fuel
Bílý, Lukáš ; Mičian, Peter (referee) ; Katovský, Karel (advisor)
This bachelor’s thesis deals with advanced nuclear fuels resistant to accidents. It focuses primarily on fuel cladding innovation. The aim was to select several concepts and then test them using the UwB1 program. The UwB1 program shows us how the multiplication factor changes during the nuclear fuel combustion process in the reactor. Based on the results, one concept was then selected.
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Nuclear Fuel in Operational Conditions
Konopová, Tamara ; Novotný, Filip (referee) ; Katovský, Karel (advisor)
This thesis deals with the issue of nuclear fuel. Firstly, the problem of nuclear fuel in the implementation for pressurized water reactors is presented. Production of nuclear fuel is introduced, which includes the performance of companies engaged in the production of this fuel. Secondly, problems of nuclear fuel during operation, focusing on burnable absorbers and phenomena in the fuel burnup are discussed. Lastly, the calculation is carried out and gadolinium as a burnable absorber is compared with erbium as a burnable absorber.
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Experimental and calculational analyses of new generation nuclear fuels
Tioka, Jakub ; Mičian, Peter (referee) ; Števanka, Kamil (advisor)
The search for Accident tolerant fuels (ATF) which is the first part of this thesis is currently one of the most actual topics in the field of nuclear fuels. These fuels must be first successfully tested in operational and also accident conditions for their possible inclusion in commercial use. Following part of the thesis specifically focuses on the boiling crisis in nuclear reactors which can damage the nuclear fuel cladding. Therefore, it is necessary to know the critical heat flux value and the departure from nuclear boiling ratio. Calculations which determine critical heal flux value are placed in the practical part of the thesis. Calculations are compared with the data obtained during experiments. The ALTHAMC12 and the other correlations which are based on the previous measurements are used for the computational analysis.
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Current Status of Nuclear Fuel Assemblies Inspections at Nuclear Power Plants World-Wide
Fendrychová, Michaela ; Temelín, Elektrárna (referee) ; Katovský, Karel (advisor)
This bachelor thesis deals with post irradiation examination (PIE) of spent nuclear fuel. The document briefly introduces basic light water reactor types (BWR, PWR, VVER) and construction of nuclear fuel for these reactors. Typical fuel failure types are described as well as methods for detection of such defects or failures. Consequently inspection methods suitable for commercial nuclear power plants are described. The primary goal of this thesis was to analyze existing inspection methods and to propose improvement of existing PIE at Temelín nuclear power plant. Therefore part of this thesis is devoted to description of fuel used at Temelín power plant, inspection methods currently applied at Temelín power plant and discussion of possible improvements of PIE.
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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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Nuclear Fuel for Pressurized Water Reactors
Smetana, Jan ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This bachelor thesis deals with structural characteristics of nuclear fuels, where most of the attention is paid to pressurized water reactors. The examples of the nuclear fuels implementation for each reactor type are mentioned for reader's better understanding. A brief history of pressurized water reactors is also listed, VVER reactors particularly. The nuclear fuel development for pressurized water reactors is demonstrated on the example of the development of fuel for our nuclear power plants Dukovany and Temelin, changes of fuel structure are emphasized. In the thesis there is also carried out a computational comparison of several selected parameters of used nuclear fuel during the operation of the nuclear power plant Dukovany.
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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 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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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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