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FACTORS LIMITING LIFE TIME OF NUCLEAR POWER PLANTS WITH PRESSURIZED-WATER REACTORS
Křivánek, Robert ; Kolat, Pavel (referee) ; Liszka, Ervin (referee) ; Fiedler, Jan (advisor)
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.
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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 plants and their safety
Novotný, Petr ; Köbölová, Klaudia (referee) ; Milčák, Pavel (advisor)
The bachelor thesis deals with the current state of nuclear energetics. It describes the development of nuclear power plants to date and specifically describes the most commonly used types of nuclear reactors. Most of the reactors currently in operation are second generation reactors. However, a number of third-generation reactors with improved technological and safety parameters are already under construction. Improved safety lies in the improvement of active safety systems, but also in the increased use of passive safety systems. The paper concludes with a comparison of specific solutions from the most important nuclear reactor manufacturers in the world.
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Aplikace SW Apros pro vytvoření modelu bezpečnostního systému JE Dukovany
DOLEŽAL, David
In nuclear power plants, we encounter a number of safety systems that complement, replace or assist each other and thus reliably perform their safety functions. A number of advanced tools are currently used to develop and test these safety systems, which must meet not only industry standards but also legislative regulations and directives. These tools include the very powerful industrial simulation program Apros 6 Nuclear, which was developed directly for use in nuclear power plants, and is therefore able to help meet the requirements of nuclear power plants in the field of nuclear safety. Within the theoretical part of this work, the issues of safety of industrial units, safety of nuclear facilities and demonstration of the Apros 6 program itself, including a description of the work in this program, are presented. This therefore means acquaintance with the most important terms used in nuclear safety, with the structure and classification of safety systems used in nuclear power plants and with the basic principles used in the field of nuclear safety. The last theoretical chapter introduces the Apros 6 program itself, the basic tasks that can be performed in it and which were used in the practical part to create a model structure. After getting acquainted with the theoretical contexts, the practical part of the work emphasizes the characteristics of a specific safety system of the primary circuit of Dukovany NPP and the implementation of the model of this safety system in the program Apros 6 Nuclear. The content of the model is an introduction and description of all the most important parts together with their settings and location.
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Creation the results book by the modeling and predictions of the effects of a radiological emergency situation on a nuclear power plant in the Czech Republic.
FRIŠTIKOVÁ, Klaudia
The aim of the thesis is creation the results book by the modeling and predictions of the effects of a radiological emergency situation on a nuclear power plant in the Czech Republic and assessment of selected input values on the results of calculations. The thesis is divided into the theoretical part, practical part and discussion, which evaluates the results of the thesis. The theoretical part uses information from the literature, which describes the ionizing radiation, its properties and effect on the population and the environment. Then, nuclear power plants, their service and possible radiation emergencies are described per valid legal regulations. End of theoretical part describes the activity for intervention in the event of a radiation emergency. The practical part describes model situations of radiological emergency situation in the vicinity of a nuclear power plant in the Czech Republic. For this thesis is selected a nuclear power plant Dukovany, for which these events are created. The results and impacts of model situations will be evaluated with the help of SW tool and then will be determined protective measures and procedures for eliminating aftermath of these incidents. Per the practical part is created an analog catalog, which will act as a backup in case of SW tool malfunction.
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Nuclear power plants
Krakovský, Matej ; Špiláček, Michal (referee) ; Milčák, Pavel (advisor)
The bachelor´s thesis explains different types of nuclear reactors and their fuel and safety characteristics. The thesis is complemented with history and description of nuclear powerplants in Slovakia. There are mentioned some of the experimental projects, whose usage is expected in the future. In the beginning are described fundamentals of nuclear energetics and nuclear fission chain reactions.
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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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Czech nuclear law
Jebas, Petr ; Damohorský, Milan (advisor) ; Humlíčková, Petra (referee)
The topic of this diploma thesis is Czech Nuclear Law. The nuclear law is a set of legal norms concerned with the ways and conditions of usage of nuclear energy and ionising radiation, the systems used to protect people and the environment against the damaging effects of ionising radiation, protocols to be followed in the case of accidents, radioactive waste disposal as well as the role of the state administration in supervising usage of nuclear energy and ionising radiation. A short historical review of the usage of nuclear energy and ionising radiation is followed by 2 chapters dedicated to international and EU nuclear law. The aims and content of international and EU collaboration concerning non-military usage of nuclear energy and ionising radiation are defined in these chapters. The other chapters of this thesis are concerned with Czech Nuclear Law. The constitutional foundation of this Law is described as well as nuclear law as a legal subject and the rules forming the base of Czech Nuclear Law. The following section deals with the power characteristics of the individual state authorities in the field of non-military usage of nuclear energy. Attention is paid to the classification of ionising radiation sources and characteristics of the tools used by the legal norm for environmental...
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European and Czech Atomic Law in the Context of Energetic Law and Environmental Law (Rennaissance or Declaine)
Klobouček, Eduard ; Damohorský, Milan (advisor) ; Stejskal, Vojtěch (referee) ; Tomoszková, Veronika (referee)
European and Czech Atomic Law in the Context of Energetic Law and Enviornmental Law (Rennaissance or Declaine) Abstract This dissertation thesis deals with recent developments in atomic law in the Czech Republic, the European Union and in international field. In the Czech Republic, the new Act No. 263/2016 Coll., The Atomic Act, which became a public codex of atomic law, is a legislation that encompasses nuclear safety, radiation protection, radioactive waste management, shipments of nuclear materials and other radioactive sources, security of nuclear materials and nuclear facilities, radiation emergency management, radiation monitoring and non- proliferation of nuclear weapons. Atomic Act replaced the old Act No. 18/1997 Coll. in which only civil liability for nuclear damage remained in force. At European Union level, a serious development can be observed lately, when new directives have been adopted to regulate radioactive waste management, nuclear safety and radiation protection. Recently, the Convention on Supplementary Compensation for Nuclear Damage and the Annex to the Convention on the Physical Protection of Nuclear Material has entered into force internationally. The new Atomic Act attempted to respond to these European and international documents and to implement and transpose their demands into...
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European directive on nuclear safety: Council decision making in 2004, 2009 and 2014
Kulda, Tomáš ; Weiss, Tomáš (advisor) ; Tomalová, Eliška (referee)
Even though nuclear energy was one the first areas in which European countries started integrating their policies through the European Atomic Energy Community (Euratom), the question of nuclear installations safety was only addressed by the EU in the context of the impending enlargement of the Union in 2004. In 2003, the European Commission submitted the first-ever proposal for a European directive on nuclear safety. However, the Council rejected it the following year, opening a five-year-long debate leading to the drafting of a new directive proposal, which was subsequently adopted in 2009. Only two years later, in the wake of the 2011 Fukushima disaster, amending this directive became necessary. Discussions resulted in adopting the amended legislation in the summer of 2014. This master's thesis analyses the main factors influencing the Council's decision-making on either rejecting or adopting the proposed directives in 2004, 2009 and 2014. The analysis is based on the following five scope conditions supposed to lead to integration acceptance by EU member states, as defined by authors Manuele Citi and Martin Rhodes: policy failure and availability of a successful alternative, external influence emanating from foreign countries hardly manageable by the individual states, functional interdependence...
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