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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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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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Pressure vessels pressurized water reactors
Horváth, Radovan ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
The aim of this bachelor thesis is the development of research on the topic of the pressure vessels of pressurized water reactors. Next is to outline the various design solutions of pressure vessels of pressurized water reactor. The thesis is divided into five chapters, contains 1 chart and 7 graphics. The theoretical part is dedicated to the history of nuclear energy and the development itself in the world. The description of the classifications of nuclear reactors is also included in the theoretical part. Summary of the theoretical part consists of a detailed description of the pressure vessel and pressurized water reactor itself. Practical part of this thesis contains the design of 3D assembly model and its modification in the program Catia V5. The overall model is composed of a main assembly, namely the body of the reactor and sub-assemblies, which were gradually installed.
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Power and Temperature Coefficient During Nuclear Power Unit Operation
Smetana, Jan ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This master thesis deals with the possibilities of traffic of nuclear power unit at thermal and power effect at the end of the campaign, focusing on VVER reactors. For a better idea of the reader the design of key components of the unit in terms of performance is analysed. Parameters of relevant components for Dukovany NPP are presented briefly. The possibilities of traffic of nuclear power unit on thermal and power effect at the end of the campaign are particularly demonstrated on the example of the Dukovany NPP. Furthermore the program Moby-Dick is introduced and the basic possibilities for its use to calculate the course of the campaign are described. At the end of the thesis, we conducted sample calculations for the duration of the campaign on the fourth block of the nuclear power plant.
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Nuclear Fuel for Pressurized Water Reactors
Smetana, Jan ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This bachelor thesis deals with structural characteristics of nuclear fuels, where most of the attention is paid to pressurized water reactors. The examples of the nuclear fuels implementation for each reactor type are mentioned for reader's better understanding. A brief history of pressurized water reactors is also listed, VVER reactors particularly. The nuclear fuel development for pressurized water reactors is demonstrated on the example of the development of fuel for our nuclear power plants Dukovany and Temelin, changes of fuel structure are emphasized. In the thesis there is also carried out a computational comparison of several selected parameters of used nuclear fuel during the operation of the nuclear power plant Dukovany.
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Subchannel model of APR1400 reactor core
Kazimov, Nurmet ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
Diplomová práce popisuje metodiku subkanálové analýzy. Subkanálová analýza slouží jako cenný nástroj při hodnocení bezpečnosti provozu jaderných reaktorů. Výsledky získané z analýzy subkanálů poskytují zásadní informace pro hodnocení rizika vzniku krize varu, stejně jako hodnocení účinnosti umírněnosti a produkce plutonia v palivových tyčích. Aby toho bylo dosaženo, je nezbytné vyvinout a validovat model aktivní zóny v v subkanálovém kódu. Diplomová práce se tímto postupem zabývá v případě aktivní zóny reaktoru APR1400. Výsledky jsou porovnány s experimentálními daty a dalšími výsledky simulace, aby validovat přesnost modelu.
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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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Nuclear Fuel for Pressurized Water Reactors
Smetana, Jan ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This bachelor thesis deals with structural characteristics of nuclear fuels, where most of the attention is paid to pressurized water reactors. The examples of the nuclear fuels implementation for each reactor type are mentioned for reader's better understanding. A brief history of pressurized water reactors is also listed, VVER reactors particularly. The nuclear fuel development for pressurized water reactors is demonstrated on the example of the development of fuel for our nuclear power plants Dukovany and Temelin, changes of fuel structure are emphasized. In the thesis there is also carried out a computational comparison of several selected parameters of used nuclear fuel during the operation of the nuclear power plant Dukovany.
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Power and Temperature Coefficient During Nuclear Power Unit Operation
Smetana, Jan ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This master thesis deals with the possibilities of traffic of nuclear power unit at thermal and power effect at the end of the campaign, focusing on VVER reactors. For a better idea of the reader the design of key components of the unit in terms of performance is analysed. Parameters of relevant components for Dukovany NPP are presented briefly. The possibilities of traffic of nuclear power unit on thermal and power effect at the end of the campaign are particularly demonstrated on the example of the Dukovany NPP. Furthermore the program Moby-Dick is introduced and the basic possibilities for its use to calculate the course of the campaign are described. At the end of the thesis, we conducted sample calculations for the duration of the campaign on the fourth block of the nuclear power plant.
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|
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Pressure vessels pressurized water reactors
Horváth, Radovan ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
The aim of this bachelor thesis is the development of research on the topic of the pressure vessels of pressurized water reactors. Next is to outline the various design solutions of pressure vessels of pressurized water reactor. The thesis is divided into five chapters, contains 1 chart and 7 graphics. The theoretical part is dedicated to the history of nuclear energy and the development itself in the world. The description of the classifications of nuclear reactors is also included in the theoretical part. Summary of the theoretical part consists of a detailed description of the pressure vessel and pressurized water reactor itself. Practical part of this thesis contains the design of 3D assembly model and its modification in the program Catia V5. The overall model is composed of a main assembly, namely the body of the reactor and sub-assemblies, which were gradually installed.
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