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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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Enrichment and reprocessing of nuclear fuel
Janoušek, Petr ; Elbl, Patrik (referee) ; Sitek, Tomáš (advisor)
Nuclear fuel is one form of electricity generation. This bachelor thesis deals with its modification and processing as this fuel has to undergo special processes to ensure its good usability. The aim of the thesis is to list and analyze the main processes involved in the production of nuclear fuel. The thesis is, in particular, focused on the enrichment of nuclear fuel, which is the process of enhancing its properties. The first and second chapter of the paper discusses basic issues of first nuclear energy and then nuclear fuel. The third chapter of the thesis explains in detail the enrichment of nuclear fuel and also describes different methods of enrichment. Another process taking place after nuclear fuel is used is it's reprocessing. This method of converting used fuel into fuel that can be reused is dealt with in the last chapter of the thesis.
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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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Advanced nuclear reactors’ promising fuels
Kadlec, Miroslav ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
This bachelor thesis focuses on the development of nuclear reactors and the fuel burned them. Thesis describes the various types of nuclear fuel, including the ways they are treated either before or after use in a nuclear power plant. Also included is a description of the situation of nuclear power plants in the Czech Republic and the Slovak Republic. In conclusion focuses on the state of some upcoming projects of the future.
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Nuclear Fuel and its Behavior during Burn-up
Matocha, Vítězslav ; Foral, Štěpán (referee) ; Katovský, Karel (advisor)
The point of this bachelor’s thesis is to characterize different types of nuclear fuels and their behaviour during the process of burning-up. Futher, basic types of nuclear reactors are mentioned, as well as their history and different kinds of nuclear fuels used in these reactors. Then there are pieces of information about fuel cycles and fuel burning-up. Furthermore, the thesis concentrates on the changes, which happen in the nuclear fuel during the process of burning-up, such as swelling and cracking. In its other parts, this bachelor’s thesis deals with fission products, mainly gas fission products are mentioned here. At the end of this thesis, a simple model of nuclear fuel burning-up is created. This model follows concentration of izotopes of uranium and plutonium during fuel burning-up.
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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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Nuclear Fuel Cycle of Temelin NPP
Ježek, Martin ; Zlámal, Ondřej (referee) ; Katovský, Karel (advisor)
This bachelor's thesis deals with the central part of a fuel cycle in the power plant of Temelín. It describes generally the whole fuel cycle, from the process of uranium mining up to permanent storage of burned-up material and it shortly mentiones possibilities of its remaking. Neverthless, the main point is the middle part of the fuel cycle. In the next parts, the thesis concentrates on the power plant of Temelín. It describes shortly the WER-1000 reactor, which is being used there, and the active zone as well. There is a further description of both fuels used there, a fuel form a Russian corporation of TVEL, which is used nowadays, as well as a fuel from an American corporation of Westinghouse used in the past. The thesis then deals with the development of a fuel cycle from the moment of launching the power plant up to the present. The problems with the fuel from the American corporation are mentioned here as well. Then it concentrates on more-than-year long cycles and tries to quantify their contribution. The thesis contains a very simple project of an elongated fuel cycle and his evaluation from the point of working economy and organisation of shutdowns.
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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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Research and Development of Innovative Uranium Nuclear Fuel Matrices
Hrbáček, Tomáš ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
The bachelor thesis is focused on the issue of nuclear fuel used for nuclear reactors. It is dedicated to research of current trends in nuclear pellets. The qualitative parameters of nuclear fuels are described here, predominanly thermal conductivity and density of nuclear fuel. A special chaper of this thesis is devoted to the simulation and fuel additives during burnout. The final part of the bachelor thesis is dedicated to a specific design of material for a test research pellet.
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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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