This thesis deals with the influence of the discharges of the Dukovany Nuclear Power Plant ("Dukovany NPP") and the assessment of impacts on the population and the vicinity of the power plant. The thesis summarizes the issues of tritium 3H discharges into waterways and partially deals with the 14C discharges. Attention is paid especially to the radioisotope of hydrogen 3H, due to its chemical and physical form and its presence in the cooling medium (light water) used by that type of nuclear power reactor. The thesis also contains a description of the current state of the Dukovany NPP, especially the existing discharges of the radioactive substances to the surroundings of the nuclear power plant, both to the air and into the waterway. Also was discussed the issue of the new planned blocks of the Dukovany NPP and impacts of the projected discharges on the population during the simultaneous operation of the existing blocks and the planned blocks, again in relation to the 3H discharged into the waterway. The application ESTE AI was used for the determination of individual groups of inhabitants who are most exposed to the radioactive discharges (also called representative person). Based on the current discharges of the Dukovany NPP and the planned blocks discharges were determined the annual effective doses for a representative person. The doses were compared with the legislation on the conditions for the peaceful use of nuclear energy requirements and then with the water management legislation. In order to avoid exceeding these limits were set up recommendations how to dispose of radioactive substances optimally. The thesis answer to the research question: What impacts on the population will have discharges of the Dukovany NPP after the construction of a new nuclear source, especially in relation to the discharges of the 3H into the waterway and which measures will must be applied on the optimization of the inhabitants doses.

In this work, which deals with problematics of releases from nuclear power plants, I tried to make an overview of various types of nuclear power plants and radioizotopes which are released through liquid and gasseous effluents. As a part of this comparison evaluation of czech and world nuclear power plants gaseous and liquid releases was made. Introductory part of this work contains information about different types of nuclear power plants and radioizotopes, which are produced in their reactors. It continues with today{\crq}s legislative and information about releasing levels and methods and systems used for measurement of radioactive gaseous and liquid effluents from nuclear power plants. Second part of this work describes the aim of this work and hypothesis. Third part explains the methods, which were used for completing of this work. Fourth part contains results in the form of tables and graphs. Fifth part represents discussion of the results. Last part is a summarization of the results.

This work deals with monitoring of the radiocarbon in the gaseous effluents from the Temelín nuclear power plant and its distribution in the environment. The reader should gain a comprehensive image about level of radiocarbon monitoring in ventilation systems in the Temelín nuclear power plant and in the surrounding environment. The work is divided into several parts. Some basic information of physics, chemistry and radiobiology relating to radiocarbon are given in the first part. The origin of radiocarbon in VVER reactor, its pathway to gaseous releases and then to carbon cycle in the environment are described there too. This introductory part continues with description of monitoring methods used in ventilation systems of the Temelín nuclear power plant and in the surrounding environment. Summary of Czech Republic legislation related to radiation protection is stated. The aim of the work and hypothesis are set in the second part. In the third part there are methods used to fulfil the aim of the work. The results in the form of tables and graphs are in the fourth part. In the following part there is a discussion of summarized data and results. Developed findings are summarized in the last part of this work.

Vitellogenesis in two caryophyllidean cestodes Caryophyllaeus laticeps and Khawia sinensis, parasitizing cyprinid fishes, were examined using light(LM)and transmission electron microscopy(TEM)and cytochemical staining for glycogen. Mature vitelline folicles consist of vitelline cells at various stages of development and an interstitial tissue. Maturing and mature vitellocytes contain vitelline material in the form of single small shell globules, which fuse and give rise to the large shell globule clusters.Glycogen was present in the cytoplasm and in the nucleus of the mature vitellocytes. Small lipid droplets were found in the cytoplasm of C. laticeps. "Lamellar granules" were observed in the cytoplasm of the mature vitellocytes in K. sinensis.

This thesis aims to propose and formulate the growth strategy for ZPA Nová Paka, a.s. company, that produces and sales measurement and control technologies for selected nuclear energy markets in the EU. The theoretical part deals with a basic strategic growth premise analysis, an analysis of the external and internal factors and a risk analysis. The analytic part contains a complex macro-environmental SLEPT analysis, a Porter five forces model analysis of branch competition and a 7S analysis of the internal environment. These results will purpose a means of reducing the strategy-related risks and options of generating profit after the return of the investments.

The members of the genus Anguis are widely but hidden living reptile species in the Czech and Slovak Republic. Due to their slight morphological characters among species of the genus, presence of two out of five species in the study area has only recently been confirmed. However, a detailed knowledge about their distribution, contact zones or potential hybridization is still unknown or very insufficient. In this master thesis, 407 individuals of Anguis fragilis and A. colchica out of 281 locations were genotyped. 407 sequences of the mitochondrial marker ND2, 170 sequences of PRLR and 156 sequences RAG1 (both nuclear markers) were used for the genetic analyses. The results confirmed the dominant species A. fragilis for the Czech Republic and A. colchica for the Slovak Republic. The contact and potential hybrid zone has north-south direction from northern Moravia and Silesia, across the Morava River valleys to the Little Carpathians and the Danubian Lowland in Slovakia. The most important information of this thesis is about potential hybridization of these species. My analyses reveal that high number of individuals in the north-south direction zone has hybrid genotype. It allowed detecting the width of the hybrid zone and more accurate genetic structure among species and populations. In addition,...

The thesis deals with the issue of nuclear energy. Within thesis we focus on attitude of Germany, Japan, Czech Republic and Slovak Republic. We assess their energy policy and transition to renewable energy. The first chapter deals with importance of nuclear energy in European Union. The second chapter is focused on new opportunities in the energy sector and concept of smart cities. The third chapter analyzes the energy of Japan, the fourth chapter the energy of Germany and the fifth chapter is focused on energy of Czech Republic and Slovak Republic.

The Diploma thesis on the topic of Increased performance turbomachinery in EDU the NPR changing describes in detail some important devices of technology system of the secondary circuit of Dukovany Nuclear Power Plant together with their task in the thermal circulation. There is a computational model of secondary circuit according to the present thermal schema created in the main part of the thesis. At the end of the thesis, the possibilities of the increase of the terminal power of turbomachinery, specifically of the turbogenerator, by the exhange of low-pressure heaters (NPR) are stated. Obtained results are documented by drawings of the thermal schemes.

The aim of the thesis is to analyze the state of preparedness of nuclear power plants (NPP) for long term operation (LTO) based on the IAEA SALTO (Safety Aspects of Long Term Operation) peer review service, analysis of the most significant failures, accidents and operational experience with type reactors PWR/VVER focusing on cases caused by equipment ageing and identification of major structures and components limiting life time of PWR/VVER-type nuclear power plants, and possible measures to ensure their required service life. Based on the results of the IAEA SALTO peer review service, an analysis of the main deficiencies and measures of NPPs in preparation for a safe LTO was performed, focusing on topics whose deeper knowledge is important for the future more precise determination of technical factors limiting the lifetime of NPPs. The main deficiencies and measures in the preparatory phase for LTO and the most important technical measures are summarized in chapter 4.5. The main deficiencies and the most important technical corrective measures in the area of ageing management of structures and components are discussed separately. The history of major failures and operational experience of nuclear power plants with PWR/VVER reactors from the point of view of ageing of structures and components is analyzed in chapter 6.2. The result is a statistic analysis of ageing-related events, an overview of the most significant PWR/VVER reactor failures with an impact on their service life, a statistical overview and discussion of the most important degradation mechanisms, and other important findings from the history of major failures and operational experience. Chapter 6.3 analyzes factors limiting the operation of nuclear power plants with PWR/VVER reactors with focus on structures and components potentially limiting the life of PWR/VVER reactors and possible measures to ensure their required life. In conclusion, the main reasons of permanent shut down of NPPs (actual and potential) for 40, 60 and 80 years of operation and the measures to ensure their required life are summarized.

The main aim of this thesis is the model design and control the secondary circuit block VVER 440. The search part of my work is a description of the secondary circuit. In the first part of the calculation is performed for the rated secondary circuit. The second calculation part focuses on the calculation circuit of the secondary for the reduced, influenced by shutting down one steam generator.