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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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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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Modern nuclear reactors
Šimík, Michal ; Suk, Ladislav (referee) ; Maar, Tomáš (advisor)
This bachelor’s thesis creates an overview of particular types of nuclear reactors, their history, present and future. Large part focus on the objectives required by modern nuclear reactors provided an international forum GIF. Reactors of fourth generation are characterized also their advantages and disadvantages. In the last section is detail description of selected type of reactor.
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Seismic resistance of the proposed pipeline route
Čapičík, Martin ; Nížňanský, Ľubomír (referee) ; Fuis, Vladimír (advisor)
The main goal of this thesis is seismic analysis and evaluation of given pipe line. In the first part we offer an overview of the modern seismic analysis methods utilized in nuclear power plants. In the following part we discuss the process of calculating of an assigned pipe line by means of equivalent static method in FEM Software Ansys 13. Based on the outcome we picked the least favourable load cases, which provided input data for determination of coefficients of safety and HCLPFMO34. Finally, the least favourable results are compared using the volume-solution and the analytical beam model in the Mathematica 8 software.
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Simulation of Accelerator Driven Nuclear Reactor for Spent Nuclear Fuel Transmutation
Jarchovský, Petr ; Ing. Antonín Krása, Ph.D., SCK.CEN Mol (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with usage of burn-up (spent) nuclear fuel in nuclear power plants of next generation – accelerator driven transmutation plants which is produced in current nuclear power plants. This system could significantly reduce the volume of dangerous long-lived radioisotopes and moreover they would be able to take advantage of its great energy potential due to fast neutron spectrum. In the introduction are listed basic knowledge and aspects of spent nuclear fuel along with its reprocessing and the possibility of further use while minimizing environmental impact. As another point detailed description of accelerator driven systems is described together with its basic components. In addition this search is followed by individual chronological enumeration of projects of global significance concerning their current development. Emphasis is placed on SAD and MYRRHA projects, which are used like base for calculations. This last, computational part, deals with the creation of the geometry of subcritical transmutation reactor driven by accelerator and subsequent evaluation which assembly is the most effective for transmutation and energy purposes along with changing of target, nuclear fuel and coolant/moderator.
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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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