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Front and Back End of the Nuclear Fuel Cycle
Winterová, Radka ; Mastný, Petr (referee) ; Katovský, Karel (advisor)
In this bachelor thesis author deals with the topic of nuclear power fuel cycle and the particular differences that are typical for each nuclear reactor types. The author aims to describe in detail both - the front and especially the back end of the nuclear fuel cycle, fuel fabrication for light water nuclear reactors, fuel reprocessing and recycling, and consequently fuel production based on REPU and MOX. Thesis should also get familiar with global approaches to fuel cycle, especially the back end.
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Nuclear Fuel Loading Patterns Optimization at VVER Reactor Based Nuclear Power Plants
Šajdler, Miroslav ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This Master’s thesis deals with optimization of loading patterns of nuclear reactors VVER. In the thesis is described the process of both types of fuel cycle – the closed and the open one. The middle part of fuel cycle containing the optimization process represents the crucial part of the thesis. The thesis is focused on the fuel cycles of the nuclear power plant Dukovany. The problem of the optimization is solved by using different programs. In the final part of the thesis, the program Athena for the loading patterns optimation is explained by a practical calculation for different versions of Moby-Dick macrocode and the calculated values for the optimization of the third unit of the nuclear power plant Dukovany are compared.
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Nuclear fuel cycles of Dukovany NPP
Peroutková, Alena ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
This thesis describes types of nuclear power plants, construction of pressurized water reactor, principle of fission processes and energy release. There is more detailed described how reactor works, following chapter of quantities describing operating status. Also is described whole fuel cycle from the uranium extraction to the used fuel storing. Next part of thesis is describing all campaigns of the Dukovany nuclear power station. Thesis also defines steps leading to increasing effectivity energy utilization. This is shown on many graphs and tabs. At the end of thesis, there is a calculation of specific uranium consumption.
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Fuel cycle, efficiency and safety of nuclear power plants
Treblík, Tomáš ; Köbölová, Klaudia (referee) ; Milčák, Pavel (advisor)
This bachelor thesis explains nuclear power plants, mainly the description of the nuclear fuel cycle. At the beginning, the principle of nuclear fission and a description of the thermal cycle are explained. The work also describes different types of nuclear reactors divided by generation. The main focus of this work is the fuel cycle, where various technologies of uranium ore mining, its processing, enrichment, fuel rods and subsequent handling of spent fuel are described. The final part describes the effectiveness of nuclear power plants in terms of thermal efficiency, as well as safety and environmental impact.
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Ionizing Radiation, Residual Heat Generation, and Inventory of Spent Nuclear Fuel
Hájková, Barbora ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This bachelor's thesis deals with ionizing radiation, residual heat generation, and inventory of spent nuclear fuel. It introduces types of ionizing radiation and half-life of isotopes, which are contained in the nuclear fuel. Furthermore, using code UwB1, a simulation of the burning of nuclear fuel used at the Dukovany Nuclear Power Plant from the introduction of fuel into the reactor to its storage in deep repositories in 2065, is carried out.
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Analysis of the innovated nuclear fuel with FEMAXI code
Čásar, Ondřej ; Novotný, Filip (referee) ; Foral, Štěpán (advisor)
This bachelor thesis deals with modification of source code of program FEMAXI 6 and subsequent analysis of composite nuclear fuel based on SiC admixture. First part introduces the entire open fuel cycle, from the start of the mining to the final disposal of the nuclear waste. The following part describes physical processes in the fuel, especially the processes associated with the low thermal conductivity of classical uranium oxide ceramic pellets, contains the description of the temperature calculations in the pellet and the analysis of the thermal conductivity coefficient including the influences affecting its size. One part of the thesis is an analysis of selected composite fuels increasing the thermal conductivity and introduction of a computational program for FEMAXI 6 nuclear fuel analysis, including its structure, implementation of equations and description of the input file. In the practical part, one can find a description of performed program modifications, comparison with other computational programs and analysis of possible composite nuclear fuel for Dukovany NPP.
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Nuclear Fuel Margins Increasing at Nuclear Power Plant Dukovany
Vrábel, Radek ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
This bachelor‘s thesis deals with power uprates and the extension of the nuclear fuel cycle at Czech nuclear power plants. The beginning of this thesis aims at improving the reader’s knowledge about nuclear reactors and nuclear fuel cycle. A whole chapter is dedicated to the development of nuclear fuel cycle at the nuclear power plant Dukovany. The progress in the field of nuclear fuels complements the development of the nuclear fuel cycle, thus providing visible benefits.
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Nuclear fuel cycles of Dukovany NPP
Peroutková, Alena ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
This thesis describes types of nuclear power plants, construction of pressurized water reactor, principle of fission processes and energy release. There is more detailed described how reactor works, following chapter of quantities describing operating status. Also is described whole fuel cycle from the uranium extraction to the used fuel storing. Next part of thesis is describing all campaigns of the Dukovany nuclear power station. Thesis also defines steps leading to increasing effectivity energy utilization. This is shown on many graphs and tabs. At the end of thesis, there is a calculation of specific uranium consumption.
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