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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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The emergency response organization of NPP Temelín operator
KOŠŤÁL, Jaroslav
This work deals with Organization of Emergency Response in NPP. According assignment this work summarizes its legal preconditions and consequently gives description of its practical realization. The necessary terminology is gathered and the basic overview of OER functioning is given. An attention is paid to staffing, structure and number of workplaces, the used documentation and also to the system of its readiness and functionality verification. The intent is to define the essential aspects of nuclear safety and to describe system of emergency planning and response in condition of real nuclear facility. In the second part of work a comparison of Stress Tests of EDU and ETE NPPs in the reason to evaluate how the goals of Emergency Response are met. The comparison of Stress Tests results is done in shape of tables. My interpretation of the established facts is: 1.The probability of earthquake exceeding the design resistant of structures, technological systems and structures is practically insignificant. The results are for both locations virtually identical. The project robustness of ETE NPP to earthquakes is slightly higher than EDU. 2.The flooding robustness of both our NPP sites is high. Both NPPs are due to its location very resistant to rain water flooding. To ensure a high level of resistance to rain water flooding requires regular maintenance of drainage systems. 3.EDU and ETE NPPs are resistant to earthquakes and in this way they are resistant to the extreme weather condition especially to the gusty wind too. 4.Secured power internal consumption supply systems on EDU and ETE NPPs are projected according to analogical basics and are enough robust to failure from common cause. To secure safe down-cooling of reactor unit the only one independent power supply system is sufficient. In project of ETE NPP there is in comparison with EDU NPP the next system of common independent power consumption supply. It is primarily intended to prevent damages in technology of secondary circle. Two DGs strongly improve the resistance of unit to SBO accident. 5.Heat removal from separate technological systems is on both power stations realized by using of analogical cooling system. Constructional differences in projects of our power stations are given by different time of their project works. There is a possibility that cooling systems of EDU NPP will be improved. 6.System of severe accident management is organized in the similar way at both facilities. The staff of Accident Board and Technical Support Centre is analogical. Recently the staff of TSC was reinforced to improve its ability to cope the multiply accident on several units. The documentation for solving of abnormal states, accidents and severe accidents has got the same basic structure. Procedures and guidelines are continually improved. Attention is paid to verification and validation of these procedures. 7.On the basis of performed Stress Tests there is a high possibility of gradual realization of partial administrative, personal and technological improvements that will be done in reason to improve Nuclear Safety and Organization of Emergency Response. The specific measures are summarized in the National Action Plan. An absolute elimination of an accident is impossible, but the probability of an accident with fuel degradation must be as low as it is reasonably possible to achieve. The NPP must be able to diminish the impacts of such event to the generally acceptable low. The ability to manage such events is the major goal of Emergency Response that should be taken as a sophisticated interdisciplinary system.
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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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The Role of G7/G8 in the World Economy - Selected Aspects
Matei, Tatiana ; Stuchlíková, Zuzana (advisor) ; Hnát, Pavel (referee)
The position of Group of Eight is today very important from the world ecomomic view. The aim of this bachelor thesis is to summarize the impact of the evolution of this group and to describe some selected influential areas more detailed. The author of the thesis sums up the origin of the group including the present influence on the world in the first part of the thesis. The next chapter contains descriptions of some of the most important aspects of the world economy. In particular, these are topics which involve the debt relief of developing countries, poverty reduction, nuclear safety, international security and terrorism.
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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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