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.

This thesis solves the problem of design and production of a special mounting device for the impeller nut of the main circulation pump GCN-317. The proposed device is intended to solve the problems associated with the mounting and dismounting of this nut. The work provides basic information about the Dukovany Nuclear Power Plant and VVER-440 systems in general, including their brief history. It also introduces the operational and legislative environment of the primary circuit of the nuclear power plant. It deals with the task and technical description of the main circulation pump and its overhaul. The following sections present the basic principles of construction of the device and an overview of its components with a description of their purpose and method of production. The last part of the thesis describes the function of the device and its verification and reports on its deployment.

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.

The thesis deals with the analysis of the grid node operation after the connection the nuclear unit. The aim of the master´s thesis is to describe the influence of network´s faults to a nuclear unit. Thesis is dealing with three fundamental problems. An influence of short circuits and power imbalance on the synchronous generator of nuclear power plant and its operation of the island network. The thesis is focused especially on the nuclear unit. However, in the case of any failure in the network, it´s necessary to check other units and their protections in the test system because unit failure could cause the disintegration of the power network. For the purposes of the simulation a test system of the power network has been developed. The test system was optimized in the LUG software, which is used to calculate the power network. Transient simulations are performed in the MODES software. Single faults are configured with scenarios. Results are generated into output files. Analysis of influence network´s faults on the synchronous generator of nuclear power plants. The ability of the synchronous generator to restore the primary steady state or hold the new steady state during changes in operating parameters of the network is one of the important parts of the safe and reliable operation of the power network. During the short circuit the damped transient actions occur. With the extension of the short circuit duration, the amplitude of the transient action increases. The risk of the stability loss of a synchronous generator increases. Therefore, the critical clearing time of a short circuit is being defined, which is the time when there is not any loss of stability. Critical clearing time of research generator is sufficient to turn off the short circuit with the help of its protection (the worst case is 0,8 s). For example, by comparison with the hydroelectric power plant, the critical clearing time is much longer. Models of other power plants have been designed with high reliability so in the case of these faults, it doesn’t cause the disintegration of the power network. Creation of island grid is characterized by strong current surges. Units must be resistant to these surges. In the island grid fast changes of the electrical parameters often occurs. Therefore, units must respond to these changes as quickly as possible and in the broadest limits. For this purpose an island operation regulator is being used. In the case of surplus island grid in steam power plants a dump condenser can be used. This is an important ability of steam power plants because the units are able to react quickly to changes of electrical parameters in island grid. The main result of this thesis is the behavior of the nuclear power plant during various faults in the power network. Researched generator of the nuclear power plant is highly stable against faults in the power network based on the findings. The results allow to continue in this topic with real network and real unit of nuclear power plant.

This Master’s thesis focuses on calculation of power and temperature distribution in fuel assemblies of VVER-440 reactor at Dukovany Nuclear Power Plant. Theoretical section contains a brief description of VVER-440 technology, fuel and its development at Dukovany Nuclear Power Plant, basics of heat generation in nuclear reactors as well as an overview and categorization of computer codes, used for core calculations. Of these codes, the MOBY-DICK computer code is then described in depth, including its input and output files. The MOBY-DICK code is later on used for pinwise calculating power distribution of selected fuel cycles of defined units at Dukovany Nuclear Power Plant, with vizualization of output values for characteristic fuel assemblies. Results of this computation are then used for analysis, whether uneven power distribution in the core and heat generation gradient within fuel assemblies have any influence on measuring channel output temperatures, which is the pivotal part of this thesis.

This thesis deals with the analysis of warming and starting up the nuclear unit of Dukovany NPP after the outage. First part explains the various operating modes of nuclear power plants, specifically operating modes of Dukovany NPP. The following part contains the analysis of heat sources in the primary circuit and also the individual production and consumption of steam by the NPP. The next part deals with division into several points of the warming of the Dukovany NPP. The analysis of warming nuclear unit after a outage is made on the basis of the industry based data, measured in December 2015. The result of the analysis is determination the amount of steam passing from a another nuclear unit, which is following by the own proposal of the external steam source.