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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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Performance of Composite Nuclear Fuels during Normal Operation and Nuclear Reactor Accidents
Foral, Štěpán ; Valach,, Mojmír (referee) ; Haščík,, Ján (referee) ; Katovský, Karel (advisor)
Tato práce se zabývá oblastí kompozitních jaderných paliv založených na UO2 . V práci je vyjmenováno několik materiálů vhodných jako aditivum ty jsou srovnány z několika různých hledisek. Byla vybrána kombinace UO2 + SiC pro detailní analýzu. Bylo zjištěno, že tato kombinace vykazuje dobré parametry v průběhu normálního provozu. Uvolňování plynných produktů štěpení je nižší společně s tepelně-mechanickým namáháním. Nicméně, je potřeba vyvinout nové modely chování kompozitních paliva. Analýza havárie blízké typu LOCA ukazuje, že palivo UO2 + SiC vykazuje poněkud lepší parametry ve srovnání s UO2 . Centrální teplota je nižší a mechanické namáhání je rovněž nižší. Na druhou stranu, analýza RIA havárie ukázala možné potíže. Například, zvýšená tepelná vodivost byla pravděpodobným důvodem zvýšené maximální teploty pokrytí a umocněné krize varu. Toto zjištění se pravděpodobně týká všech paliv založených UO2 , které mají zvýšenou tepelnou vodivost pomocí dopantů.
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Trends in nuclear fuel development
Takács, Gergő ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
The aim of the bachelor thesis is to acquaint the reader with the differences between pressurized water reactors of the eastern and western type. It describes the differences in the materials used in the cladding and describes the concepts of individual fuel assemblies. It devotes a section to the various events that occur between the fuel and the cladding during the fission reaction. It also gives an overview of what the largest companies are dealing with, describes future trends in the development of nuclear fuel.
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Design of the steam generator for modular reactor
Černý, Marian ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
Subject of this thesis is design of the steam generator for modular reactor. The dissertation consist of the theoretical part, where are described heat-exchangers and steam generators used in nuclear power plants. Second part contains theoretical calculations in the first approach (thermal, hydraulic and strenght calculation). In the next part are particular variants of steam generator selected. For the final variant are necessary calculations (introduced above) and drawings of selected parts are done. In the final statement is technical solution evaluated, and the parameters of the steam generator are compared with actually used steam generators.
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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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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 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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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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Nuclear fuel cycles of Dukovany NPP
Peroutková, Alena ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
This thesis describes types of nuclear power plants, construction of pressurized water reactor, principle of fission processes and energy release. There is more detailed described how reactor works, following chapter of quantities describing operating status. Also is described whole fuel cycle from the uranium extraction to the used fuel storing. Next part of thesis is describing all campaigns of the Dukovany nuclear power station. Thesis also defines steps leading to increasing effectivity energy utilization. This is shown on many graphs and tabs. At the end of thesis, there is a calculation of specific uranium consumption.
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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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