This Master´s thesis deals with the coordination and the order of interventions during the appearance of a major accident due to a blackout. It describes in detail the chronology and the priorities of what the shift engineer should do when working on the self-consumption restoration. Furthermore, it gives the variants for determination of the batch of radiation people are obtained by, while working on the self-consumption restoration.

The present Master´s thesis aims at designing an evolutionary scheme of secured power supply at nuclear power plants with VVER 440 reactors during design basis accidents as well as design extension conditions. In the first part of this thesis, concepts relating to the defence in depth of nuclear reactors, operating modes of the blocks as well as types and possibilities of electrical power supply and electric circuits of the block are defined. Although the present thesis deals with PWR 440 in general, special emphasis is put on the Czech NPP in Dukovany, where there are four PWR 440 reactors in operation, and on the possibilities for enhancing the defence in depth in this area. The second part of the thesis deals with the difference in station blackout definitions before and after Fukushima; not only the differences in situation evaluation are dealt with, but a solution is also proposed to make the system of secured power supply system during design basis accidents as well as design extension conditions more robust. This option has been selected out of a number of possibilities based on the evaluation of reliability, availability and cost-effectiveness of the proposal.

This thesis introduces reader to current knowledge of nanomaterials and their usage. It summarises production methods and usage of different materials in nuclear power plants, nuclear research and nuclear medicine. Theoretical part of this thesis is dedicated to possible usage of carbon nanotubes for neutron beam collimation and guides. In experimental part different materials were tested in measuring box connected to horizontal radial channel of VR-1 nuclear reactor and their influence on neutron flux was measured. Tested samples were non-oriented carbon nanotubes, carbon nanofibers, alumina nanowires, oriented carbon nanotubes with several angles of rotation and these samples were compared with results of graphite.

This thesis describes the provision of the data communication of the new protection relays via 6 kV switch gears to the electro monitoring system at the Dukovany Nuclear Power Station. These protection relays will replace the current analog protection. The replacement process will start in 2015 and will finish in 2018. Given the overall complexity of the project, this thesis deals only with the following 6 kV switch gears 9BB and 9BD. The thesis is divided into a theoretical and a practical part. The theoretical part concerns the actual consumption and output of the Dukovany Nuclear Power Station. The following chapters describe the electro monitoring system and GRAF and LOGA software programs that are closely connected with it and that were used in the practical part. The last chapter of the theoretical part deals with the actual replacement of the protection relays of the 6 kV switch gears. Also, it describes a new optical network, which will be set up at the Dukovany Nuclear Power Station as a part of the process of replacement. The segment of the practical part concerns laboratory verification of the data communication of the new protection relays. Next, it describes actions that had to be taken in order to ensure and verify correct functionality of the data communication. This part is followed up by a closely related practical activity, which describes examination and verification of the protection functions of each of the 9BB and 9BD switch gears protection relays.

Author´s name: Bc. Stanislav Klimek School: Brno University of Technology, Faculty of Mechanical Engineering, Energy institute Title: Determining the life storage of a carbon steel cask Consultant: Prof. Ing. Oldřich Matal, CSc. Number of pages: 70 Year: 2009 The assignment of this diploma thesis is to estimate the lifetime of spent fuel container made from carbon steel grade. This container is designed for deep geological disposal of spent nuclear fuel. Basic mechanism of corrosion are described in detail in the first part. Further on, this work deals with the other specific phenomena and influences, which affect at corrosion of steel in conditions of a deep geological repository. Heat, radiation and surroundings are considered of particular importance. In the following part an estimate of the lifetime of model container is introduced, which is affected by temperature and radiation. Here recommendations for protection of container are introduced, arising from the model calculation. Finally, the relevancy of incidence of particular parameters is evaluated, which affect the corrosion.

This diploma thesis deals with nuclear energetics and its impact to the environment. Present state of the energetics, mainly nuclear energetics, in the Czech Republic is discussed here. Also perspective of nuclear energetics is given. The thesis describes nuclear power plant waste handling and also spent nuclear fuel handling. Nuclear power plant is compared with other sources of electric energy, which are counted to the energetic mix. The author focuses on fossil fuels and also on the renewable energy sources. The amount of produced waste to the unit of produced energy, built up area, safety and economic indicators and other parameters are followed for each source of energy.

This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Dukovany Unit No. 3. In general damage mechanisms of reactor steels are described and possibilities of monitoring of material degradation and its recovery used at NPP’s all over the world are mentioned as well. A practical part of the thesis is focused on interpretation of analyses carried out with the assistance of MOBY DICK code. The ground of these analyses is a neutron fluence value development on different locations of RPV for the whole life of operation up to 24th cycle. The analyses results are put into context with performed in-service inspections. The thesis follows up with neutron fluence computation for the future cycles containing new types of nuclear fuel up to 34th cycle. The outcome of practical part of the master‘s thesis is a comparison between new types of nuclear fuel with respect to radiation damage of RPV’s.

Interactome of IL-1α N-terminal domain Cytokines are highly effective mediators produced by various cell types within and outside of the immune system with the aim to influence the orientation, intensity, and duration of the immune response and inflammatory process. Their biological effects mediated through binding the high-affinity membrane receptors and triggering the signal transduction pathway are usually well defined. However, as it is more and more frequently observed, in addition to the exocrine function, some cytokines may show intracrine effects. For this type of cytokines, the term "dual function cytokines" has been adopted. One of these cytokines is Interleukin-1α, in which the recent research has concentrated on determining its intracellular functions. The intracellular function of interleukin-1α has not been clearly defined so far. However, apart from the absence of the conventional hydrophobic sequence, its existence is supported by the fact that the N-terminal peptide included in its precursor is highly conserved and contains nuclear localization signal. The aim of this work is to define the conditions of localization of the interleukin-1α N- terminal domain in different cellular compartments and to study proteins potentially interacting with it using fluorescent microscopy. Key words:...

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This Master's thesis dealt with securitization attempts related to the planned construction of a new reactor at the Dukovany NPP. Therefore, its aim was to find, analyse and explain securitization speech acts associated with the planned reactor, in the period from summer 2015 to December 2020 using the critical discourse analysis approach. The results show that securitization speech acts of this kind do appear in the Czech public sphere and are articulated mainly by four groups of actors: representatives of Austria, Czech environmental NGOs, Czech governmental representatives, and Czech political opposition. These actors have different goals: to stop the construction of the reactor, to implement the construction of the reactor, or to influence the way in which the construction will be implemented. One case of successful securitization was found in the outcome: The Czech government was able to enforce extraordinary measures that deviated from standard democratic processes using security-based arguments. Their goal was to implement the construction of the reactor. It remains to add that the research also revealed three important functional actors who co-created the discourse: the BIS secret service, the SÚJB nuclear safety office and the company ČEZ.