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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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Ways of radioactive materials saving in the Czech Republic and in the world
Polák, Luboš ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
Management of spent nuclear fuel and radioactive waste are many. The aim of this thesis was to summarize the attitude of the Czech Republic and the other major countries on this issue. First is given the classification of radioactive waste according to various criteria. Consequently, it is defined and described the fuel cycle, as the largest producer of all types of radioactive waste. Then is analyzed approach of the Czech Republic to the management of all type radioactive waste and the attitude to deep geological repository. At the end are some, in this respect, major countries and their attitude to deal with spent nuclear fuel, radioactive waste and the method of final disposal.
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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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Radiation damage of VVER-440 based Dukovany NPP reactor pressure vessel investigation
Říha, Tomáš ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Dukovany Unit No. 3. In general damage mechanisms of reactor steels are described and possibilities of monitoring of material degradation and its recovery used at NPP’s all over the world are mentioned as well. A practical part of the thesis is focused on interpretation of analyses carried out with the assistance of MOBY DICK code. The ground of these analyses is a neutron fluence value development on different locations of RPV for the whole life of operation up to 24th cycle. The analyses results are put into context with performed in-service inspections. The thesis follows up with neutron fluence computation for the future cycles containing new types of nuclear fuel up to 34th cycle. The outcome of practical part of the master‘s thesis is a comparison between new types of nuclear fuel with respect to radiation damage of RPV’s.
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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 certain reactors is presented. Production of nuclear fuel is introduced, which includes the performance of companies engaged in the production of this fuel. Secondly, the phenomena in the fuel burnup are discussed. Lastly, the burnable absorbers are mentioned and the analysis of burnable absorbers is carried out.
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Study of alternative ending of nuclear fuel cycle in the Czech Republic
Michalica, Jaroslav ; Radil, Lukáš (referee) ; Šťastný, Ondřej (advisor)
This bachelor thesis deals with the alternative end of the nuclear fuel cycle in the Czech Republic. At the beginning of the work, the nuclear fuel cycle is explained, then the radioactive waste, how it is produced, and how we divide it. This is followed by a chapter that deals with the removal of the used nuclear fuel, from its extraction from the reactor through its temporary storage until its final disposal in an underground waste repository. The work then explains the alternative of direct disposal of used nuclear fuel, namely reprocessing of used nuclear fuel. It explains the existing methods for the reprocessing of used nuclear fuel which are currently being used, and where the used nuclear fuel reprocessing plants are located. The conclusion of the thesis deals with the economic comparison of direct final disposal of used nuclear fuel with reprocessing and final disposal of radioactive waste.
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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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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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Study of alternative ending of nuclear fuel cycle in the Czech Republic
Michalica, Jaroslav ; Radil, Lukáš (referee) ; Šťastný, Ondřej (advisor)
This bachelor thesis deals with the alternative end of the nuclear fuel cycle in the Czech Republic. At the beginning of the work, the nuclear fuel cycle is explained, then the radioactive waste, how it is produced, and how we divide it. This is followed by a chapter that deals with the removal of the used nuclear fuel, from its extraction from the reactor through its temporary storage until its final disposal in an underground waste repository. The work then explains the alternative of direct disposal of used nuclear fuel, namely reprocessing of used nuclear fuel. It explains the existing methods for the reprocessing of used nuclear fuel which are currently being used, and where the used nuclear fuel reprocessing plants are located. The conclusion of the thesis deals with the economic comparison of direct final disposal of used nuclear fuel with reprocessing and final disposal of radioactive waste.
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