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Czech nuclear law
Künzel, Karel ; Damohorský, Milan (advisor) ; Humlíčková, Petra (referee)
89 Abstract The topic of the thesis concerns Czech nuclear law. Nuclear law can be defined as a set of special legal norms adjusting the terms of the nuclear energy and ionizing radiation usage, protection of population and environment against ionizing radiation, radiation accidents solving and treatment of radioactive waste. As such, nuclear law fully adjust the behaviour of all the natural and legal persons who are concerned with activities connected to the nuclear materials, ionizing radiation and natural resources of ionizing radiation. The field of nuclear law is closely connected to the branches of science dealing with the nuclear energy and ionizing radiation usage; therefore, the factual issues of which at least the fundamental knowledge is necessary for the understanding of nuclear law are given space at the beginning of the thesis. In its provisions, Czech nuclear law adjustment also reflect a number of international treaties and European Union regulations. On account of this, the next part of the thesis deals briefly with the international and European nuclear law adjustment. Important international organizations of the field are mentioned as well. The core of the paper consists in the part concerning the outline and analysis of the present adjustment of Czech nuclear law. The taxonomy of this...
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The concept for passive cooling of the VVER-1000 reactor
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis is focused on the design of passive cooling system for a nuclear reactor VVER- 1000.This type of reactor is located in the Czech Republic in the location of Nuclear power plant Temelín. The thesis states an overview of the different cooling systems of nuclear power plants. The thesis is focused on passive safety system especially on passive cooling system, so there was done an overview of currently used passive safety system. In the work is discussed nuclear safety and the maximum projected accident of VVER-1000, which is called LOCA accident. In the design part of the thesis was done thermal calculation of heat exchangers. Exchangers are designed as condensers with a natural flow, where cooling of system is provided by outside airflow in case an accident. The results are evaluated at the end of the thesis.
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Nuclear Power Plant Dukovany Tasks within an Electricity Grid of the Czech Republic
Prokop, Ondřej ; Řež,, Martina Malá, Centrum výzkumu (referee) ; Katovský, Karel (advisor)
The aim of the Bachelor’s thesis is to describe the role of The Nuclear Power Plant Dukovany (Dukovany NPP) in the Czech electricity grid. Increasing of the production of electricity from renewable energy sources in the electricity grid causes more frequently compliance of N-1 criterion and it decrease the reliability of the electricity grid. The risk of Blackout increases, which would cause large economic losses and danger to the life of human beings. Therefore, reliable, good controllable and safety sources of electricity are very important. The first part of the thesis describes the role of Dukovany NPP in the process of regulation of basic electrical parameters during the normal operation of electricity grid. The second part of the thesis deals with states and the function of Dukovany NPP after full or partial disintegration of the electricity grid. Final part analyzes the importance of Dukovany NPP in Czech electricity grid and future development Dukovany NPP with possibility of the construction of new nuclear units after the end of the operation in 2035. The Dukovany NPP is an important regulator of the reactive power. There isn’t other power plant in the southeastern part of the Czech Republic, which could significantly control reactive power. The power from Dukovany NPP, which is provided on ancillary services controlling the real power and frequency has been increasing in recent years. This is due to the increasing production of renewable sources. Units switch to island operation after partial disintegration of electricity grid. If frequency exceeds the limit, the units will switch to it is own consumption. In this stage of operation at own consumption can Dukovany NPP operated without the time limit. Dukovany NPP may participate in restoring the electricity grid, based on dispatch control instruct. If switching to own consumption is not successful and back up sources and emergency’s dieselgenerator are unavailable, the power supply has to be restored as soon as possible. There are six independent solutions to restore the power supply. Next option of restore power supply will be the AAC network after the completion of construction in 2014. The AAC network will be resistant to the extreme weather and will be place it in the area of the power station, thereby Dukovany NPP will be more independent on external network.
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Accidents of light water reactors
Bejček, Patrik ; Novotný, Filip (referee) ; Foral, Štěpán (advisor)
This thesis deals with the description of primary and secondary circuit of nuclear power plant with reactor VVER-400. Moreover, this thesis describes nuclear safety, its particular factors, and also international nuclear event scale. It is followed by a description of companies playing a significant role in the field of nuclear safety and a close attention is paid to SÚJB. In a section dedicated to nuclear safety, the focus is on events which can occur in nuclear power plant. In addition, the accident Large Break LOCA is described in detail. The practical part deals with the description and instructions to simulator PCTran developed by Micro-Simulation Technology. In the last part, there is an analysis of selected parameters which are simulated in simulator PCTran, parameters simulated in simulator RELAP5 5 and also the calculation of the temperature parameters of fuel TVSA-T and their simulation.
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Benchmarks and test facilities of VVER reactors
Šimek, Ondřej ; Foral, Štěpán (referee) ; Vojáčková, Jitka (advisor)
The aim of this bachelor’s thesis is to describe the topic of benchmarks and test facilities for pressurized water reactors of the eastern concept VVER type. The theoretical part introduces the VVER type reactors, their history, the development of separate generations, including fundamental differences and parameters of the VVER type reactors being used so far. Next two chapters of the theoretical part focus on nuclear safety and security, describing the uppermost Czech authorities, which are SÚJB, MAAE and NEA. Furthermore, many terms concerning nuclear safety are explained in these two chapters. The next chapter is focused on deterministic safety analyzes, their classification, methods and purposes. The aim of this part is also to explain the verification and validation of computing codes. The next chapter offers insight into test facilities which are crucial for evaluation and testing of nuclear devices and computing codes. The last chapter of the theoretical part focuses on the VVER type reactor benchmarks. The practical part of this thesis presents the conversion of a single AER Benchmark FCM_001 using neutron physical code PARCS. The results are compared to the results of CRONOS computing code.
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Depletion calculation of VVER 1000 reactor fuel using KENO code
Janošek, Radek ; Katovský, Karel (referee) ; Novotný, Filip (advisor)
The introduction to operational nuclear reactors focusing on light-water pressurized reactor VVER 1000 is in the beginning of this Master´s thesis. This thesis covers basic technology of VVER 1000 reactor with focus on reactor core and nuclear fuel TVSA-T. A significant part of the thesis deal with basic concepts of nuclear safety and its methods. The main goal is to create a model of VVER 1000 reactor, which can be used in nuclear burn-up calculations using KENO code. Therefore a part of this thesis deals with explanation of statistical Monte Carlo method and the KENO code.
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Approach to the nuclaer safety of the 3rd generation nuclear reactors
Pavlíček, Michal ; Kolář, Jaroslav (referee) ; Kolář, Jaroslav (referee) ; Matal, Oldřich (advisor)
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.
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Safety assessment of Temelin NPP
KOŠŤÁL, Jaroslav
History of peaceful use of nuclear energy, despite of all necessary emphasis on operation safety, is accompanied by a series of accidents, some of which left indelible trace in minds of wide public and so led to changes in the comprehension of nuclear safety and in the access to its preservation. Because the consequences of possible nuclear power plant accident have always serious social impacts, it is most desirable to define all possibly risks, to quantify probability of their formation and in this way to gain the possibility to prevent them effectively and efficiently. This work is dedicated to approve or to disapprove that the KARS method is practically applicable for evaluation of nuclear power station operation safety. The work objective is to evaluate events and risks associated with the operation of a particular nuclear facility by the KARS method and critically evaluate obtained results and the used method as such. The work is divided into theoretical and practical part. Theoretical part includes basic information necessary for correct understanding of the chosen data processing procedure and subsequent interpretation of the gained results. A brief overview of basic concepts relating to the nuclear safety, the safety culture and the emergency preparedness, including their definitions is given in this section of the work. For the evaluation of obtained results it is useful to make familiar with basic concepts of the NPP safety evaluation, PSA and the stress tests. Obviously, it is necessary to describe the KARS method and to define the concept of quality of human performance with regard to the obtained results. The risk analysis by the KARS method was carried out in the four consecutive steps: 1. Data collection for the risk analysis. 2. Data processing by the use of the KARS method. 3. Interpretation of the obtained results. 4. Comparison of the obtained results with the available data. The particular risks for the construction of the risk correlation table were based on the analysis of activities of individual members of the emergency and technical support center on the basis of managing documentation for each function. In the emergency instructions these risks are either named or the action to manage them are determined. Subsequently these risks are further more specify according to the operational documentation used for solving abnormal and emergency conditions or solving of severe accidents. Determination of the risk correlation seems to be subjective and requires a considerable degree of professional insight into the analyzed issues. The risk analysis was processed according to the procedure that was laid down by Ing. Stefan Pacinda, Ph.D. Each risk taken into consideration in this analysis is briefly described within the interpretation of obtained results. The coefficients of activity with the biggest value were found for these risks: human error, earthquake, plane crash, terrorist threat, errors in operating and managing documentation and fire. The coefficients of passivity with the biggest value were found for these risks: human failure, serious damage to health, ecological disaster, components malfunctions, radiation accident, nuclear material integrity damage and control system malfunctions. Comparison of the risks that were postulated in the stress tests and the risks that were considered in this analysis indicate that the ETE NPP emergency response was prepared to be able to cope these risks. Results of this analysis showed that the essential element for the safe operation of nuclear power plants is qualified, well selected and systematically trained staff. In light of the experience acquired during elaboration of this work I have concluded that the KARS method can be used for nuclear safety evaluation only in a limited way.
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Population protection in the emergency planning zone around the Nuclear Power Plant Temelín
MARTINŮ, Pavlína
This issue represents contribution to discussion of the population protection within the emergency planning zone of Temelín Nuclear Power Plant (NNP). My intention was to evaluate the actual system of public protection measures in the case of potential appearance of the radiation accident. As a part of this evaluation the analysis of correlation between emergency classification system of emergency events severity, valid for Temelín NPP, and system of immediate protective measures for population was done. The introductory parts of my work describes the basic information about Temelín Nuclear Power Plan. The main attention was given to nuclear safety, radiation protection, principles of emergency preparedness and types of NPP operating modes. Further system of public protection measures for the case of radiation accident appearance is described. Emergency classification system of potential extraordinary events at Temelín NPP and principles of announcements and public warning is also explained in this part. Part of this information represents description of potential implementation of immediate protective actions. One of the outputs is in the form of simple educational software program useful especially for children education. They can received information how to behave in the case of radiation accident declaration. Software is enclosed in the form of compact disk and gain knowledge can be verified by a short test.
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Enterprise management and environment
Martenek, Milan ; Dvořák, Jiří (advisor) ; Syrovátka, Oldřich (referee)
Graduation theses deals with problems of nuclear energetics and its impact on the environment. It presents the progress of nuclear power station in all contexts and tries to demostrate that the nuclear energetics is unavoidable progression. The work further describes the influence of Nuclear power station Dukovany on its close environment, especially on animals, plants and the health of inhabitants.
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