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.

At the nuclear power plant accident, the radionuclides with very short half-life come to enviroment, they decay the period from several second to several months. On the other sides come to enviroment radionuclides with long half-life. Their radionuclides occur in surrounding of the power plant for hundreds of years before they decay totally. Immediately after a nuclear power plant accident, radioiodine represents the most severe health hazard for population. Because it is a radionuclide with short half-life, it causes the danger during first months after the accident. Its health hazard lies in the fact, that it gets to food chains and irradiates a man, who consumed contaminated water and food. Radiocaesium and radiostrontiom are the next important radionuclides. They have long half-lifes, it means that will decay after hundred years after the accident and they endanger population a long time after the accident yet.

This master thesis has been conducted at Forsmark nuclear power plant. In nuclear power plants, safety is one of the most important tasks. After the Fukushima-accident, Forsmarks Kraftgrupp AB investigated the possibility to have additional emergency cooling systems. This thesis aims to investigate the use of cooling towers as mobile emergency cooling system for decay heat removal for the nuclear reactors at Forsmark NPP. The advantages and disadvantages of different cooling tower types were looked at. To achieve mobility, some restraints were considered such as dimensions and weight. In the design of cooling towers, experimental values are used. As these crucial data are missing, a backfitting from actual designs was done to derivate the missing data. The results of this thesis show that wet cooling towers are in this case more effective than dry cooling towers. The wet cooling towers cover in the best scenario up to 38MW which is 10 times higher than what can be achieved with the dry cooling tower. That covers the maximal decay heat released in the reactor F3 12 hours after a shutdown.

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.

This diploma thesis focuses on the analyzing the current state of monitoring the radiation situation by volunteer firefighters units in the emergency planning area in Dukovany nuclear power plant surroundings. The process of measurement is divided into preparation for radiation leakage and application of learned procedures in the case of the occurred radiation leakage. The aim is to identify the dangers in the current process as well as the possible risks in the case of radiation emergency by risk analysis. Based on this analysis, improvements suggestions will be made. These measures will be evaluated by their applicability and their economic value. The system of monitoring by voluntary firefighters will be compared with another monitoring system, which can be also used. The result of the analysis will be a more effective way of monitoring, including safety of the firefighter and less financial complexity.

The subject of the diploma thesis is an architectural study of the forecourt of the Dukovany Nuclear Power Station. The project is based on a pre-diploma project which aimed to develop an urban concept. At the moment the buildings in the area are in an unsuitable condition from a construction - technical and architectural perspective. The urban-architectural study was intended to create a new concept for the forecourt and simultaneously enable its efficient operation in case of the completion of a new nuclear unit. The concept of the solution is based on the removal of outdated buildings and their replacement with new buildings which will meet the current requirements of the Dukovany Nuclear Power Station. From the current layout the main roads, the gatehouse, the information center and the greenery will be preserved. After removing the selected buildings, the renovation area will be divided into the main axes on which the main road network will be designed. The unsuitable connection to public road infrastructure will be solved by minimizing the entrances to the area to two entrances and by moving the suburban bus station from the main road. After connecting the whole area by roads, the area will be divided into functional areas. In front of the gatehouse there will be a square surrounded by public services, an administrative building and by the preserved information center building. From this space, the main representative space of the entire complex will be created. Warehouses and workshops will be located behind the square. Transport areas will be located at the rear of the complex. Thanks to this location, there will be a good connection with the current factory and also with the planned completion of the new nuclear unit on the west of the area. There will also be educational and sport facilities in the complex. The kindergarten will be oriented towards the preserved greenery.

The aim of this thesis is to create a conceptual design of the secondary and tertiary circuit of a new nuclear power plant in our country, which is preceded by a brief search of particular generations of nuclear reactors. The VVER-1200 reactor became the model for the new nuclear power plant. There was designed a heat diagram containing primary components in this work. After that, there was the balance calculation and calculation of parameters of the main devices of the proposed scheme such as condenser, low-pressure and high-pressure regeneration exchangers and steam generator.

This dissertation deals with the idea of annexing a new nuclear resource in the locality of the Dukovany Nuclear Power Plant and the way of its connection to the power system. The main aim of this dissertation is to design concrete solution of the connection of the new resource to a certain point of the power system and complete this design by means of chosen calculation. According to the task, this dissertation consists of three parts. The first part describes the current engineering solution of the main one line diagram of our two existing nuclear power plants and generally of chosen types of power plants abroad, too. There is also a design of the internal consumption of the nuclear power plants. The objective of the second part of this dissertation is to present the survey of the power and dispositional variants of the new resource in view and mainly assess general possibilities of its connection. Using all information from the preceding part, the third part presents the concrete design of the engineering solution of the connection of the new resource to the power system and also the calculation of parameters of block transmission line. Another dissertation named “Study of Slavětice Distribution Substation Enlargement for EDU New Resources“ concurs this part or more precisely, my dissertation as a whole . For my dissertation I have used some materials and information from the ČEZ Corporation which are confidential. I have also used some knowledge from the analysis from the EGÚ Brno Corporation. This dissertation neither represents nor substitutes a complex analysis of all aspects of a new nuclear resource in the Dukovany Nuclear Power Plant.