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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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Nuclear power plant condenser design
Havel, Jaroslav ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The submitted bachelor’s thesis deals with the design of a condenser for the new Dukovany II nuclear power plant with an electrical output of 1,200 MW. The specified condensation parameters reflect typical parameters of pressurized light-water moderated and cooled reactors of the same power and climatic conditions in the given location. From the assignment of the thesis and the research carried out, the following requirements for the designed device emerged: to ensure the condensation of steam in the secondary circuit in filmwise condensation mode, to comply with the maximum cooling water heating of 10 K, to install the tube bundle at optimum angle and to ensure the competitiveness of the product. For the selected concept with a four-body condenser, a thermal analysis was made and solved numerically by a fixed-point iteration method. The calculation was performed using the EES software. The results showed that a heat transfer surface area of 121,263.96 m is required to ensure failure-free operation of the condenser. Each condenser body consists of 31,400 titanium tubes with a cross-section of ( 22 × 0,5) mm and a length of 14,554 mm. A dimensional drawing is also attached.
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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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Protection of Citizens before and during the Nuclear Accidents
Červinka, Petr ; Hradil, Jaroslav (referee) ; Mika, Otakar Jiří (advisor)
This work is concerned with protection of citizens before and during the nuclear accidents. There is described what threat is nuclear accident in first part of this work. Next are noted sources of risk and classification of accidents in nuclear plants. There is mentioned legislature of Czech Republic in this area and principles of protection of citizens. Part of this work is a short study of Chernobyl accident and a concept of pocket guide for citizens.
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Analysis of the condition of the K 220-44 steam turbine drainage pipeline and proposal of corrective measures
Horký, Jiljí ; Milčák, Pavel (referee) ; Šnajdárek, Ladislav (advisor)
This diploma thesis deals with the analysis of the drainage pipeline of the Škoda K 220-44 steam turbine. This turbine is operated in Dukovany Nuclear Power Plant. One part of this work is proposal of corrective measures. The aims of this work include the creation of a search for drainage, steam, erosion corrosion and mapping of defects in long-term operated drainage system. Work also includes the evaluation of measured values of the pipe wall thickness measured by ultrasonic analyzer. In addition, the work contains images created from 3D model, on which the location of defects and measurements are displayed.
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Noise Generator Diagnostics
Plucková, Iveta ; Nahodil, Petr (referee) ; Hammer, Miloš (advisor)
The bachelor thesis deals with noise diagnostics of the generator. The practical part of the thesis is realized in the Dukovany Nuclear Power Plant. The first part of the thesis, noise is generally discussed. The quantities and their measurements are described, quite generally, also for the given company. According to specific conditions in the Dukovany Nuclear Power Plant, there is a distribution of noise measurements, which is carried out by an external company. The work gives a concrete example of this measurement. At the end of the work, the practical measurements of noise were done for selected generators, which were realized by an author for the purposes of this bachelor thesis. The experiment is evaluated.
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Facelift PDU
Zhakupbekova, Rakhil ; Kyselka,, Mojmír (referee) ; Nový, Alois (advisor)
The subject of the diploma thesis is the elaboration of an architectural study of the reconstruction of the pre-plant zone of the Facelift of the Dukovany power plant. The construction site is an area that belongs to the village of Dukovany and borders the village of Rouchovany. As a whole, this area is in poor technical and architectural condition. However, its location gives potential for new uses. The solved area belongs to the ČEZ nuclear power plant.
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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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Advanced nuclear reactors’ promising fuels
Kadlec, Miroslav ; Varmuža, Jan (referee) ; Katovský, Karel (advisor)
This bachelor thesis focuses on the development of nuclear reactors and the fuel burned them. Thesis describes the various types of nuclear fuel, including the ways they are treated either before or after use in a nuclear power plant. Also included is a description of the situation of nuclear power plants in the Czech Republic and the Slovak Republic. In conclusion focuses on the state of some upcoming projects of the future.
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