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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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Changes of international organizations: the IAEA experience in Iraq and Iran
Kosub, Tomáš ; Bříza, Vlastislav (advisor) ; Parízek, Michal (referee)
This paper discusses the International Atomic Energy Agency (IAEA), and its experience from Iraq and Iran. The paper provides the reader with principal theoretical understanding of international organizations, understanding of the process of change in the IO's and then, using two separate case studies, explains problems of the IAEA during the Iraq nuclear crisis and later, during the Iran nuclear crisis. The paper afterwards discusses the changes inside the IAEA which were considered necessary after that experience. An important part of this paper is also a comparison of the new state with the previous extension of the authority of the IAEA, and how these changes improved the execution of that authority, as specified in the IAEA Status. In the end, the paper categorizes these changes into the theoretical understanding of change in the International Organizations, namely changes after the Iraq and Iran experience. The main part is, therefore, a description of the evolution of these countries' nuclear programme, and a description of the IAEA processes, tools and authority needed during the execution of these rights.
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Changes of international organizations: the IAEA experience in Iraq and Iran
Kosub, Tomáš ; Bříza, Vlastislav (advisor) ; Parízek, Michal (referee)
This paper discusses the International Atomic Energy Agency (IAEA), and its experience from Iraq and Iran. The paper provides the reader with principal theoretical understanding of international organizations, understanding of the process of change in the IO's and then, using two separate case studies, explains problems of the IAEA during the Iraq nuclear crisis and later, during the Iran nuclear crisis. The paper afterwards discusses the changes inside the IAEA which were considered necessary after that experience. An important part of this paper is also a comparison of the new state with the previous extension of the authority of the IAEA, and how these changes improved the execution of that authority, as specified in the IAEA Status. In the end, the paper categorizes these changes into the theoretical understanding of change in the International Organizations, namely changes after the Iraq and Iran experience. The main part is, therefore, a description of the evolution of these countries' nuclear programme, and a description of the IAEA processes, tools and authority needed during the execution of these rights.
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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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