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Position Improvement Using Differential GPS
Košťál, Jaroslav ; Hrubý, Martin (referee) ; Novotný, Tomáš (advisor)
The bachelor thesis describes techniques of precision of a position using a differential GPS. The theoretical part provides with basic terminology on classical and differential GPS and with a blueprint for implementation of the differential GPS. The aim of the practical part is the implementation of the blueprint per se using two suitable GPS modules with data processing on the station in real time and creation of a graphical interface. The final determining of the position should be more accurate than one using a classical GPS.
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Position Improvement Using Differential GPS
Košťál, Jaroslav ; Hrubý, Martin (referee) ; Novotný, Tomáš (advisor)
The bachelor thesis describes techniques of precision of a position using a differential GPS. The theoretical part provides with basic terminology on classical and differential GPS and with a blueprint for implementation of the differential GPS. The aim of the practical part is the implementation of the blueprint per se using two suitable GPS modules with data processing on the station in real time and creation of a graphical interface. The final determining of the position should be more accurate than one using a classical GPS.
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Knihovna pro práci se soubory formátu Office Open XML
Košťál, Jaroslav
The thesis deals with a library for working with Office Open XML Files -- spreadsheet files --, with its analysis, suggested layout, and implementation. It includes a specification of a standard spreadsheet file and of ways of creating such files. Based on studied theory, a layout is suggested for a library for reading and recording data, and for implementation of such a library in the C# language, which offers interface suitable for working with this type of documents.
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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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