|
|
Possibilities of transmutation of spent nuclear fuel with advanced nuclear reactors
Ošust, Marek ; Brně, Dušan Král, Los Alamos NL a FEKT VUT v (referee) ; Katovský, Karel (advisor)
This bachelor thesis deals with the issue of transmutation of spent nuclear fuel. It describes the accelerator driven transmutator as well as its individual components. Examples of specific projects such as MYRRHA and CiADS are also given. The main objective of the thesis is the investigation of material properties of the spallation granular target. Compounds of heavy and light elements have been considered. Their physical properties, the number of neutrons generated by interaction with impinging proton beam and the resulting neutron energy spectrum were compared. The calculations were performed using the TALYS program.
|
|
|
Photovoltaic battery with nuclear light source
Koval, Jiří ; Krbal, Michal (referee) ; Katovský, Karel (advisor)
A thermophotovoltaic battery with a nuclear light source is a complex device, converting thermal energy from radioisotope decay into electrical power. The work looks for suitable fuel, construction, materials and commercial use. Individual parts of the assembly are consistently described. Assembly include a thermal radioisotope unit, an infrared radiation emitter, an optical filter to increase efficiency, photovoltaics and cooling to remove excess heat. The problem of the individual parts is the search for the highest possible efficiency due to several transformations and large energy losses. The assembly uses nuclear fuel, produced mainly during the fission reaction in nuclear reactors.
|
|
|
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.
|
|
|
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.
|
|
|
INVESTIGATION OF PU-239 TRANSMUTATION FOR ACCELERATOR DRIVEN SUBCRITICAL REACTORS
Tanchak, Anhelina ; Parlag,, Oleg (referee) ; Krása, Antonín (referee) ; Nečas, Vladimír (referee) ; Katovský, Karel (advisor)
Tato disertační práce je zaměřena na stanovení průřezů radionuklidů vznikajících v důsledku spalační reakce v terči z plutonia (239PuO2) ozářeného protonovým svazkem o energii 660 MeV. Kromě toho byly vzniklé nuklidy zkoumány pomocí různých nástrojů za účelem zjištění jejich vlastností. K ozáření terče byl použit fázotronový urychlovač Spojeného ústavu jaderných výzkumů v Dubně jako generátor protonového svazku. Experiment byl zaměřen na hledání krátce žijících radionuklidů. Pro měření spekter gama byly použity detektory HPGe. Spektra , získaná během tohoto experimentu, byla zpracována pomocí softwaru DEIMOS32. Pro identifikaci jader vzniklých v terči 239PuO2 byl použit kód AD4HEL. Komplexní analýza těchto zbytkových produktů a jejich charakteristik významně přispívá k pochopení spalace a štěpných reakcí mezi protony a 239Pu v oblasti vysokých energií. Experimentální údaje o průřezech jaderných reakcí mohou sloužit jako referenční údaje pro teoretické simulace ke studiu reakcí a mohou být použity k doplnění jaderných databází. V komplexní analýze byly experimentální výsledky porovnány se simulacemi provedenými pomocí kódů Monte Carlo pro přenos částic, jako jsou MCNP v.6.1. a FLUKA. Výstupem z experimentálních dat je, že získaná data celkově odpovídají očekávání, přičemž mají podobné oblasti koncentrací nuklidů, analogické grafy a mírné odchylky v rozsahu hodnot. Odchylka je pravděpodobně způsobena normalizačním faktorem z důvodu omezení různých softwarových nástrojů.
|
|
|
Computational simulation of the third unit of the Dukovany Nuclear Power Plant
Musil, Michal ; Mičian, Peter (referee) ; Katovský, Karel (advisor)
Bachelor‘s thesis deals with the analysis of the possibilities of increasing the output of the 3rd production unit at the Dukovany Nuclear Power Plant. First, the primary circuit of the Dukovany Nuclear Power Plant and the development of various types of nuclear fuel are described. The theoretical part also contains a basic description of deterministic and stochastic calculation methods and a description of the MOBY-DICK calculation program. The practical part contains a comparison of several cases for which an increase of the power output of Unit 3 of the EDU would be possible. All cases are compared in terms of nuclear fuel consumption and the potential for achieving increased power output.
|
|
|
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.
|
|
|
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.
|
|
|
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.
|
|
|
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.
|
guest ::
