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Computational Analysis of Nuclear Fuel of Pressurized Water Reactors
Hřebačka, Michal ; Brně, Ondřej Šťastný, ONZHN SÚJB a FEKT VUT v (referee) ; Katovský, Karel (advisor)
This thesis focuses on calculating the multiplication factor of selected nuclear fuels for pressurized water reactors using two different computational tools. The first tool is a relatively simple code named UWB1 developed at the University of West Bohemia, and the second is the official and widely used computational system SCALE. The results of both programs are compared using a set of fuels used at the Dukovany Nuclear Power Plant with further discussion on their operational and economic characteristics. The final part is dedicated to the analysis of the geometry of fuels offered by final vendors in connection with the Dukovany II project.
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Innovative nuclear fuels and simulation of their burn-up
Pibil, Vojtěch ; Lovecký,, Martin (referee) ; Katovský, Karel (advisor)
The thesis deals with advanced nuclear fuels with increased accident tolerance. The work summarizes the solutions of nuclear fuel manufacturers, describes their problems and advantages over the currently used fuel. In the next part, calculations are performed on uranium tellurides and germanides fuels. The results of these calculations are then used to determine whether any of the tellurium or germanium isotopes behave as a burnable absorber.
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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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Spent nuclear fuel and its properties
Jestřáb, Tomáš ; Řež,, Martina Malá, Centrum výzkumu (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to develop fuel depletion models of a nuclear fuel used at Nuclear Power Plant Dukovany – originally designed nonprofiled fuel used in a three-year cycle, inovated profiled fuel used in a four-year cycle and currently used fuel Gd-2M+ used in a five year fuel cycle. Models are created by computational code UWB1 providing fast calculation of nuclear fuel depletion. Outputs of these models are in thesis graphically displayed and analyzed from the point of view of fuel depletion, enrichment or irradiation time spent in reactor core. These analyses are based on theory including information about the nuclear fuel cycle focusing on its middle part and the back end of the nuclear fuel cycle.
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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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Spent nuclear fuel and its properties
Jestřáb, Tomáš ; Řež,, Martina Malá, Centrum výzkumu (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to develop fuel depletion models of a nuclear fuel used at Nuclear Power Plant Dukovany – originally designed nonprofiled fuel used in a three-year cycle, inovated profiled fuel used in a four-year cycle and currently used fuel Gd-2M+ used in a five year fuel cycle. Models are created by computational code UWB1 providing fast calculation of nuclear fuel depletion. Outputs of these models are in thesis graphically displayed and analyzed from the point of view of fuel depletion, enrichment or irradiation time spent in reactor core. These analyses are based on theory including information about the nuclear fuel cycle focusing on its middle part and the back end of the nuclear fuel cycle.
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