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Small and modular reactors on the map of the Czech Republic
Šimůnková, Radana ; Brně, Kamil Števanka, OR NJZ MPO a FEKT VUT v (referee) ; Katovský, Karel (advisor)
The future development of the energy sector is linked to the 3 D - digitalisation, decarbonisation and decentralisation. This group could be expanded to include a fourth D - diversification of resources. Since the second half of the 1980s, the use of nuclear energy has been an integral part of the Czech energy sector. With the development of nuclear energy, small modular reactors are often mentioned today. The construction of small modular reactors could help transform the energy mix, which needs to be adapted to the imminent end of coal use for energy purposes. This thesis contains a detailed description of potential sites for the future location of small modular reactors in the Czech Republic and analyses the individual sites using the author's methodology. An overview map with potential sites was created in QGIS software. Furthermore, the thesis summarises and describes the most promising small modular reactor projects and evaluates them according to the methodology recommended by the International Atomic Energy Agency. Finally, the thesis proposes the consideration of additional sites with regard to the potential use of waste heat.
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The Impact of Load Folowing in Providing System Services of the Selected Dukovany Power Plant Unit on the Parameters of the Core
Kaňa, Jiří ; Ing. Jakub Lüley, PhD., ÚJFI FEI STU v Bratislave (referee) ; Katovský, Karel (advisor)
To operate safely and reliably, the power grid needs power sources that are capable of providing flexibility. In the scenario that emission-free sources dominate the energy mix, the provision of these services will largely be the responsibility of nuclear power plants. Changing the output of a nuclear power plant is burdened with a number of specificities that need to be respected compared to the output changes of thermal power plants. This thesis explores the possibilities of using the reactor at the Dukovany power plant to provide load-following. From a theoretical point of view, it presents information on the needs of the power system, the general possibilities and limitations of using nuclear power plants for load-following and presents the historical context of this practice. After applying different scenarios of load-following, the simulation results are assessed from safety, operational and economic points of view.
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Fast molten salt reactor simulation
Dzurňák, Martin ; doc. Ing. Pavel Zácha, Ph.D., ÚE FS ČVUT v Praze (referee) ; Katovský, Karel (advisor)
This thesis deals with the sensitivity analysis of a molten salt fast reactor. The computational sensitivity analysis is carried out in the MCNP program. After an introduction to molten salt reactors and an overview of molten salt fast reactor projects, the Stable Salt Reactor - Wasteburner project is selected for sensitivity analysis. The development of the reactor model in MCNP is described. Sensitivity analysis is performed on the influence of the nuclear data library, reactor temperature and the influence of the fuel salt composition.
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Design and optimization of device for characterization and recycling of plastic radioactive waste
Hrbáček, Tomáš ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
This thesis focuses on the generation, management and monitoring of radioactive waste in nuclear power plants in the Czech Republic. After the Second World War, with the development of nuclear power and armaments, radioactive waste management became an important field. The main sources of waste are the nuclear fuel cycle and a variety of industrial, research and medical activities. This work focuses on the detection of gamma radiation on plastic foils that are used as protection during reactor maintenance shutdowns. The objective is to contribute to more efficient waste management and to promote the recycling of materials in nuclear power plants with the collaboration with the company MIFRE s.r.o.
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Simulational model of utilization of process heat in the system with advanced small modular reactors
Doležal, Václav ; SÚJB, Jan Varmuža, (referee) ; Katovský, Karel (advisor)
This thesis explores the history and current utilization of heat from nuclear power plants, particularly small modular reactors (SMRs). The work initially analyzes the historical development and surveys past projects in this area. Furthermore, it provides an overview of possible applications of heat from nuclear power plants. Subsequently, the thesis focuses on advanced projects of small modular reactors with an emphasis on the industrial use of heat. In the practical part, a system model is constructed that integrates process heat from SMRs in systems of selected potential consumers with the possibility of concurrent hydrogen production.
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Accelerator driven nuclear reactor neutron field parameters determination
Zemčíková, Kristína ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
The master thesis deals with calculation of neutron field parameters in systems controlled by an accelerator called the Accelerator Driven System (ADS). Firstly physical principle is described, along with its parts as well as the history and present of ADS projects worldwide. Subsequently, neutron activation analysis and gamma spectrometry are described in more detail. The experiment on AmBe neutron source and on Microtron MT25 is presented in the experimental part. Lastly, the reaction rates are calculated.
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Investigation of Ionizing Radiation Infuence to the Communication Systems of Satellites
Golubev, Martin ; Kubíček, Michal (referee) ; Katovský, Karel (advisor)
This master thesis discuss about ionizing radiation, interaction with matter and effects on her. In the work is discussed differend types of interactions of directly ionizing radiation and indirectly ionizing radiation. Below is an overview of methods of shielding from all of types of ionizing radiation. Second part of this thesis discuss about single event effects in semiconductors which are cause by ionizing radiation. At the end is described design of measuring instrument included FPGA chips. This design is discused both from point of wiew hardware and software too.
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Design of nuclear ceramic materials with enhanced thermal conductivity
Roleček, Jakub ; Katovský, Karel (referee) ; Salamon, David (advisor)
Oxid uraničitý (UO2) je v současnosti nejčastěji používaným materiálem jakožto palivo v komerčních jaderných reaktorech. Největší nevýhodou UO2 je jeho velmi nízká tepelná vodivost, a protože se při štěpení UO2 v jaderném reaktoru vytváří velké množství tepla, vzniká v UO2 peletě velký teplotní gradient. Tento teplotní gradient způsobuje vznik velkého tepelného napětí uvnitř pelety, což následně vede k tvorbě trhlin. Tyto trhliny napomáhají k šíření štěpných plynů při vysoké míře vyhoření paliva. Tvorba trhlin a zvýšený vývin štěpného plynu posléze vede ke značnému snížení odolnosti jaderného paliva. Tato práce se zabývá problematikou zvyšování tepelné vodivosti jaderného paliva na modelu materiálu (CeO2). V této práci jsou studovány podobnosti chování CeO2 a UO2 při konvenčním slinováním a při „spark plasma sintering.“ Způsob jak zvýšit tepelnou vodivost použitý v této práci je včlenění vysoce tepelně vodivého materiálu, karbidu křemíku (SiC), do struktury CeO2 pelet. Od karbidu křemíku je očekáváno, že zvýší tok tepla z jádra pelety, a tím zvýší tepelnou vodivost CeO2. V této práci je také porovnávána podobnost chování SiC v CeO2 matrici s chováním SiC v UO2, které bylo popsáno v literatuře.
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Experimental Investigation of Accelerator Driven Nuclear Reactors for Thorium Based Nuclear Power
Zeman, Miroslav ; ČR,, Milan Štefánik, UJF AV (referee) ; Katovský, Karel (advisor)
The Master Thesis deals with the use of thorium nuclear fuel in accelerator driven systems. Basic principle of ADS, present situation and future possibilities are described in this work. The main goal of the work is determination of neutron flux in spallation target QUINTA. In December 2013, an experiment was performed at Joint Institute for Nuclear Research, Dubna. Samples of cobalt, situated at different positions in QUINTA target, were irradiated in secondary neutron field generated by deuteron beam of energies 2 AGeV and 4 AGeV and beam of C-12 with energy 2 AGeV. The samples were measured with the use of germanium semiconductor detectors and analysed using gamma-ray spectrometry. Reaction rates of Co-59 products were determined. Neutron flux was determined in setup QUINTA on the base of experimental reaction rates. Experimental reaction rates were compared with calcula1tion of MCNPX code.
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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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