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Experimental analysis focused on the effect of chloride salt on neutron flux with different energy levels
Slančík, Tomáš ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
Master’s thesis focuses on the history and current progress in research of molten salt reactors around the world, with an emphasis placed on the properties of molten salts and the problems associated with their use. In relation to the practical part, one chapter is devoted to the creation of input file in the MCNP software. The practical part deals with neutron activation analysis of graphite prism experiment, which is filled with powder NaCl salt. This experiment is focused on the effect of salt on neutron flux with different energy levels. The whole problem was also simulated in the MCNP environment along with the experiment. At the end of the thesis, the individual methods are compared and evaluated.
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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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Reseach of Molten Salt Cooled Nuclear Reactor Behavior
Kostečka, Jan ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
The master ‘s thesis deals with the studying behavior of nuclear reactors cooled by liquid salts and with application of liquid salts for IV. Generation of nuclear reactors. For the use of liquid salts, it’s necessary to change the concept of the structure of nuclear reactors. There are new ways to use new fuel in a liquid state. Each salt compound or a set thereof is original in its nature. Therefore, it is necessary to consider a suitable compound for the purposes employed. These points are discussed in the theoretical part. The thesis examines particularly chloride salts, with which there is not much experience. The practical part monitors and verifies the nuclear properties of chloride salts, in our case it is a solid-state chloride sodium chloride’s compound. In addition to the experimental measurement, the MCNP simulation program is used also.
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Departure from nucleate boiling in nuclear reactors
Bednář, Michal ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
This bachelor thesis deals with problem of boiling crisis in nuclear reactors and how this problem influences working od nuclear reactor. This thesis is focused on power water reactors, with focus on VVER 1000 reactor type, which fuel assembly is described in this thesis in more detail. In this thesis there are described terms related to boiling crisis and two-phase flow regimes. In the last part, the thesis is dedicated to the correlations for the critical condition and individual correlations are compared.
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Overview and Utilization of Small Modular Reactors
Křeček, Tomáš ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
This bachelor thesis deals with an auspicious type of new nuclear reactors – small modular reactors (SMR). It defines the basic qualities of SMR and their essential differences among large nuclear reactors, briefly evaluates the individual advantages and disadvantages. It summarizes the history and current direction of their development in the most active countries. In the bachelor's thesis are also discusses the most advanced propositions of SMR and the possibilities of their use. In the last part is analysis of the usability of SMR in the energy mixture and the possibilities of application in the Czechia.
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Methods of neutron detection
Arbeit, Vít ; Števanka, Kamil (referee) ; Mičian, Peter (advisor)
This bachelor thesis deal with neutrons, ways to detect them and with neutron detectors themselves. The theoretical part includes description of all principles by which it is possible to detect them and defines both already established neutron detectors and the latest type of detector. The practical part is focused on realization of Bonner spheres and the measurement of their properties on a neutron source 241Am-Be.
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Experimental and calculational analyses of new generation nuclear fuels
Tioka, Jakub ; Mičian, Peter (referee) ; Števanka, Kamil (advisor)
The search for Accident tolerant fuels (ATF) which is the first part of this thesis is currently one of the most actual topics in the field of nuclear fuels. These fuels must be first successfully tested in operational and also accident conditions for their possible inclusion in commercial use. Following part of the thesis specifically focuses on the boiling crisis in nuclear reactors which can damage the nuclear fuel cladding. Therefore, it is necessary to know the critical heat flux value and the departure from nuclear boiling ratio. Calculations which determine critical heal flux value are placed in the practical part of the thesis. Calculations are compared with the data obtained during experiments. The ALTHAMC12 and the other correlations which are based on the previous measurements are used for the computational analysis.
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The concept of the heat exchanger for the IMSR reactor
Števanka, Kamil ; Katovský, Karel (referee) ; Martinec, Jiří (advisor)
Cílem práce bylo vytvořit základní koncept integrovaného výměníku tepla pro solí chlazený reaktor vyvíjený společností Terrestrial Energy s využitím programu Promex. První kapitola se zabývá historií a současnou situací v oblasti výzkumu malých modulárních reaktorů chlazených fluoridovými solemi. Ve druhé kapitole jsou popsány vlastnosti fluoridových solí a konstrukčních materiálů. Poslední kapitola se zabývá simulací tepelného výměníku pomocí programu Promex, validací modelu, transformací protiproudého výměníku na výměník s U trubkami a vizualizací výměníku s použitím CAD Invetoru.
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