This master’s thesis deals with usage of burn-up (spent) nuclear fuel in nuclear power plants of next generation – accelerator driven transmutation plants which is produced in current nuclear power plants. This system could significantly reduce the volume of dangerous long-lived radioisotopes and moreover they would be able to take advantage of its great energy potential due to fast neutron spectrum. In the introduction are listed basic knowledge and aspects of spent nuclear fuel along with its reprocessing and the possibility of further use while minimizing environmental impact. As another point detailed description of accelerator driven systems is described together with its basic components. In addition this search is followed by individual chronological enumeration of projects of global significance concerning their current development. Emphasis is placed on SAD and MYRRHA projects, which are used like base for calculations. This last, computational part, deals with the creation of the geometry of subcritical transmutation reactor driven by accelerator and subsequent evaluation which assembly is the most effective for transmutation and energy purposes along with changing of target, nuclear fuel and coolant/moderator.

The aim of this diploma thesis is to clarify fundamental principles of activities of police officers of the Regional Directorate of the Police of the South Bohemian Region in the case of radiological emergency at the Temelín Nuclear power station. These principles are concentrated in compact documentation with practical tasks for respective organizational segments of the Regional Directorate of the Police of the South Bohemian Region. This documentation will be consequently used as a methodical guide for concerned police officers. Fundamental terms are defined in the theoretical part of the diploma thesis, concerning and usable in the course of measures in the case of solving radiological emergency at the Temelín Nuclear power station. The analysis of legal standards and technical bibliography is also performed in this part. The External Emergency Plan of the Temelín Nuclear power station is presented in detail, and a comparison of the previous and current atomic law is drawn. Last chapter of this part is devoted to the actual documentation of the Regional Directorate of the Police of the South Bohemian Region to manage the radiological emergency at the Temelín Nuclear power station. Necessary number of legal regulations, agreements and internal acts of management concerning the current topic was used for elaboration of this thesis. Information and findings of employees from the Department of Emergency Management of the Regional Directorate of the Police of the South Bohemian Region are also included. The practical part of the diploma thesis is devoted to the concentration of all materials and previous findings of the Regional Directorate of the Police of the South Bohemian Region in the case of measures for radiological emergency at the Temelín Nuclear power station into individual chapters. Each of these chapters presents particular activities of police officers of the Regional Directorate of the Police of the South Bohemian Region during performation of tasks in connection with managing the radiological emergency at the Temelín Nuclear power station. When listing particular tasks and processes, some of activities of other subjects participating together with members of the Police of the Czech Republic in measures concerning the radiological emergency are also mentioned in this part. The result of this thesis is a focused overview and operative material for police officers of the Police of the Czech Republic, usable for making them acquainted with questions of managing the radiological emergency at the Temelín Nuclear power station. It also serves as a background for regular practices and training courses on this subject.

This work evaluates evolution changes of socio-economical structure and Territorial System of Ecological Stability (ÚSES) in Territory Zone. Territory Zone is meant nearer surround of river dam Hněvkovice, that is used for needs of technological water in JETE (nuclear power station Temelín). There can be found villages Buzkov, Dobřejovice, Hroznějovice, Jaroslavice, Jeznice, Kostelec, Litoradlice, Poněšice, Pořežany, Purkarec and Třitim. This work also solves evolution of number of population, age structure and employment from 1982 to 2001 as well as other specific development factors of this territory. The part of this work is the KES (Coefficient of the Ecological Stability) of the territory before and after the Hněvkovice dam was built. The basic characteristics of whole territory and list of historical interests is also important.

Fatique life extension of nuclear powerplants lies in the search for project reserves. This work deals with the evaluation of low-cycle fatigue of nuclear installations of the VVER type and the assessment of the influence of the computational model level. Fatigue tests of austenitic steel using optical method of digital image correlation for which the evaluation procedure is designed and used is performed. Selected model of plasticity with kimenatic (Chaboche) and combinated hardening (Chaboche, Voce) are calibrated from the obtained data. Subsequently, the durability of the test specimen is determined by computational modeling for different material models. From the comparison of the results of fatigue tests with the calculation, the material models suitable for the description of fatigue life and their validity are determined.

The theme of the diploma thesis is the solution of the pre-plant zone of the Dukovany nuclear power station. Creating a vision of how this space could develop further in the next 50 years and how it could work in a transitional phase during the construction of a new nuclear power plant unit. The subject of the thesis is the elaboration of an architectural study, which is based on an urban study. Urban study was processed within the framework of the pre-diploma thesis and solved mainly the overall problems of this area, the new transport connection, and the functional division of the whole area. The area was divided into three functional units, namely the transport zone, the administrative zone and the sports and education zone. At present, there are a lot of small structurally and functionally unsuitable buildings in this area. The diploma thesis deals with the design of new buildings with a clear functional use in the administrative zone, in the area in front of the main gatehouse. A new representative square was created, and three buildings are designed around it. The dominant feature of the whole area was a high-rise office building near the gatehouse. In front of the office building, towards the main road, the service building I was designed, which contains business and healthcare services. On the other side of the square was located the service building II, where there are technical services, such as workshops, warehouses and metrology. The last building solved within the diploma thesis is the building of sports and locker rooms of suppliers, which is designed behind the square near the greenery. New building copies mass of the only preserved building in this area, namely the building of the information centre. The designed building has a fitness centre and locker rooms of external workers of the power plant.

This diploma thesis deals with various ways of energetically advantageous utilization of waste heat produced by industrial technologies. The focus of the diploma thesis is both to provide an overview of different ways and places of origin of waste heat in industrial technologies and of its possible reutilization, to suggest a concrete air heating system using waste heat and to propose a long-distance hot water pipe which supplies hot water pipe system with energy. First, technologies producing waste heat and some ways of regressing of heat in such technologies are theoretically described. Second, the equipment for transferring of heat and for adjustment of thermal energy parameters is described. A special focus is put on water supplies of the Nuclear Power Plant Dukovany and some selected parts of its secondary circuit, which is waste heat collected from. The analysis is supplemented by a calculation of theoretical quantity of waste heat. The aim of the calculation is to determine whether waste heat can be a source of energy for heating. Then, a current system of heating of three selected buildings in the area of the Nuclear Power Plant Dukovany is briefly described. Based on the gained knowledge, a project of air heating with two heat pumps type water – water, a heat receiver preparing warm service water and three recuperative units for preheating of fresh heating air is designed. The selection of main parts of the air heating is amended by a calculation of purchase costs and electric energy consumption. After that, the focus is placed on choice of type of hot water pipe – its trace is stated and an indicative estimation and a thermal-conditions calculation in the hot water pipe are made. The preliminary calculation serves as a source of information for a final project of air heating and calculation of changes of temperatures longwise the hot water pipe. The project contains also a calculation of pressure losses and an analysis of economical questions concerning hot water pipes. In conclusion, the results of project of air heating and hot water pipes are summarized.

The goal of this project is to test the possibility to connect the Cogenerational generation of power 138 MW (still in the development stage) to the control room 110 kV in Prostejov production. This merge would product the electrical energy as well as the heat energy for all local area. In this dissertation we will be considering the solution of the steady state (stationary state) of system with the voltage level of 110kV, as well as the influence of the generation of power on this system, there by the suggesting a connection. The Congenerational production indicates higher effectiveness in the transformation of energy during primary production process due to the production of heat energy as well as the electrical energy from the primary power sources. In our country, as well as around the world, commonly used fuels are fossil fuels- coal, crude oil, and gas. As the demand for energy grows, those supplies are slowly running out. Not to mention that those fuels have a negative environmental impact. They are a source of carbon, which causes damage to the atmosphere and leads to global warming. Power plants which do not produce carbon are much safer for the environment, and much more productive. However, the residue of this energy is challenging to dispose of. Nuclear energy has common attributes with renewing the sources of energies that are extremely friendly to our environment. Nuclear power plants also produce enough energy and with the usage of Fourth generation reactors, they will be able to recycle the nuclear fuels. Today, more importance is put on renewing sources which are more gentle for the environment. In the near future, CEZ Company, the largest producer of electric energy is planning to use water energy. Water energy comes from water plants or dams. Other ecological forms of energy include geothermal and solar energies. These two types of energy are not as applicable for our geographical position. Geothermal energy is commonly used on islands where there is an abundance of natural hot springs. The most discussed source of energy is bioenergy. It uses natural wood sources, recycled wood products, and applies bioenergy as a main source for thermal power plants.

Diplomová práce se zaměřuje na kritické zhodnocení současné energetické politiky Evropské Unie a její dopady na účastníky trhu s energetickými komoditami, především s důrazem na energetické společnosti a koncové spotřebitele.

This diploma work is engaged in replacement of gasket main dividing plane of reactor coolant pumps in nuclear power plant Paks. Of the newly suggested gasket is kammprofile gasket with expanded graphite layer. This work contain suggestion and calculation of new sealing a knot and calculation existing sealing the knot. Results are confrontacion and sequentially is discussed influence on main dividing plane HCČ 317 by use the new and the existing gasket. In this work is contained description brief of legislation. This legislation must keep by design components dedicated for nuclear equipment. Next this work contain view of the most important sealing knots used in primary system of Nuclear Power Plant type VVER 440.

The main target of the master´s thesis is reviewing the generation III nuclear reactors in term of the nuclear safety. At first we have to learn some theory of the nuclear safety in order to understand safety systems of the generation III nuclear reactors. Therefore the thesis is divided into two parts. Legislative and technical approaches to nuclear safety are mentioned in the first part. Regulatory bodies, whose task is to supervise nuclear safety in the nuclear power plants, belongs to the legislative approaches. There are defined terms such as defence in depth, redundancy, diversity, etc. There are mentioned methods to assessing nuclear safety – deterministic and probabilistic methods, especially probabilistic methods, for which a simple example is provided. There are also mentioned active and passive safety systems and their significance for nuclear safety and inherent safety too. There is an example of the function of the active and passive safety systems of the EDU nuclear power plant in conclusion of this issue. The second part deals with description of the selected nuclear reactors in context of the construction of the new units of nuclear power plant in Temelín. The nuclear reactors from companies, which applied for the public tender opened by ČEZ, a. s., for the construction of the ETE 3+4. Thus, the nuclear reactor MIR-1200 by ATOMSTROYEXPORT (Russian Federation), the nuclear reactor AP1000 by WESTINGHOUSE (USA) and the nuclear reactor EPR by AREVA (France) are taken into account . Comparison of the generation II and these generation III+ nuclear reactors necessarily belongs to this master´s thesis. These the generation III+ nuclear reactors are compared with the nuclear reactor VVER 440 (EDU) and in particular with the nuclear reactor VVER 1000, which is operated in the nuclear power plant Temelín. The final chapter contains generally appraisal of the whole problem.