National Repository of Grey Literature 25 records found  1 - 10nextend  jump to record: Search took 0.01 seconds. 
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.
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.
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.
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.
Simulation of nuclear fuel burn-up during whole fuel cycle
Smola, Luděk ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to create a long-term kinetics model of a nuclear reactor – model, which simulates changes in nuclear fuel inside the reactor core during reactor operation. As the term long-term suggests, primarily the changes in whole five-year fuel cycle horizon are studied, which stands for changes in concentration of elements contained within fresh fuel as well as origination of new ones (with special focus on higher actinides and plutonium). This mathematical model is created using the MAPLE 14 software. Outputs from the model are displayed graphically and thoroughly analysed, so that comprehensive conclusions of problems can be made. Furthermore, the thesis contains theoretical and informational background that is necessary for understanding all the aspects of the model – historical development of nuclear reactors, their basic types, nuclear fuel description focusing on fuel for pressurized light-water reactors VVER (for which the model is primarily designed), MOX fuel and possibilities of its utilization, and last but not least – selected topics from nuclear physics.
Nuclear Fuel Loading Patterns at VVER Reactor Based Nuclear Power Plants
Šajdler, Miroslav ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
The Master's thesis focuses on loading patterns of nuclear reactors VVER. It describes the whole process of fuel cycle, since production to storage or reprocessing. The author puts emphasise on the middle part of fuel cycle in Czech nuclear power plants - Dukovany and Temelín and he also explains which fuels are used in both power plants now and which were used in history. The thesis also contains a basic overview of approaches to loading patterns optimisation in foreign countries. The final part of the thesis discusses practical calculation of loading patterns in the Block III of Nuclear power plant Dukovany, by using optimisation programme Athena and Moby-Dick macrocode.
Front end of the fuel cycle
Sedlák, Miroslav ; Katovský, Karel (referee) ; Foral, Štěpán (advisor)
Bachelor thesis will work of the front of the fuel cycle. Summarize and describe the current knowledge related to uranium, the phase transformation of unemployable chemical element for mankind significant energy source. Understanding the process of processing uranium to energy source is invaluable importance for the future of energy. The use of uranium as fuel only brings advantages inherent in the usability element for humanity, but also the disadvantege of environmental threats and the threat of negative censequences to the environment in case of accidents. A thorough knowledge of the various stages of the fuel cycle contributes to increasing the safety of use of this chemical element for mankind and increasing efficiency in the conversion of uranium ore, thereby creating still more favorable conditions for the development of nuclear energy.
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.
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.
Current Up-to-Date Research and Development in the Field of Nuclear Fuel
Koláčný, Tomáš ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
This bachelor thesis aims to characterize the currently used nuclear fuels and their materials, describe a fuel cycle from the mining, processing and enrichment, to possibe management of used fuel, neatly summarize useing nuclear reactors with their basic specifications and outline the possible trends of development of nuclear fuels.

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