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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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Study of Slavětice Distribution Substation Enlargement for EDU New Resources
Štus, Martin ; Ing. Pavel Štěpánek - ČEZ a.s.- EDU (referee) ; Matoušek, Antonín (advisor)
The aim of this diploma work has been to work up a first study dealing with possibilities of enlargement of Slavětice substation with the new sources of Dukovany power-plant (EDU). In this work I am mentioning the linking of 400 kV Slavětice substation into the electricity system in Czech Republic and its coupling into the west-European UCTE system and I am also itemizing the basic data of neighbouring substations. Further I am describing the current state of 400 kV and 110 kV substations in Slavětice, their parameters and scheme. In this work I am mentioning basic information of nuclear reactor piles, coming into consideration for the prospective new pile construction in the premises of Dukovany substation and also reflections about possibilities of bringing out power of this new pile. In the following part of my diploma work there are stated proposals of different versions for enlarging the Slavětice 400 kV substation by a new outlet of new EDU source and the eventual overhead-line construction. I am mentioning the necessary substation arrangements for each proposed version, the scheme, eventually the proposal how to lay-out the new lines. Further there is stated here a proposal of outgoing feeder switchgear accessories for the new EDU pile and also the proposal for an entirely new substation, its description and scheme. An evaluation of all proposed versions of Slavětice substation enlargement for connecting new nuclear piles is stated in the outcome of the work.
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Change in the Production of oversize Components of the Pump
Kratochvíl, Zdeněk ; Prokop, Jaroslav (referee) ; Kalivoda, Milan (advisor)
The thesis proposes a method for implementing structural changes on the compression flange of the main circulation pump, at the time of its overhaul during the unit outage. This structural modification consists in Annular groove of the groove to a diameter of about 850 mm. It is necessary to choose a suitably radius of maximum made possible smoothly rounded grooves without notches to reduce the stress of the concentration at the corners of the groove. Possibilities for making this adjustment are considered in this thesis and then the technology is selected with control torque calculations. The selected technology consists in the sizing of grooves with the mobile numerically controlled machining lathe EFCO TDF-2 NC, which is documented in the Annular groove of the axial grooves. In conclusion there are described other possibilities of using of this mobile machine in the primary circuit of a nuclear power plant.
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Accelerator Driven Nuclear Power Plants
Jarchovský, Petr ; Krása,, Antonín (referee) ; Katovský, Karel (advisor)
This bachelor’s thesis deals with utilization of spent nuclear fuel in nuclear power plants of new generation – accelerator driven nuclear power plants and of conversion of this fuel into electrical energy. In the introduction are listed basic physical and theoretical knowledge of nuclear reactors along with their basic division and global distribution. As another point accelerator driven systems are described with their brief development and the basic concept and usage on both the nuclear power plants and transmutation technologies. Some global projects are mentioned here dealing with this system and conduct research. More into detail is point about European projects MYRRHA and ESS, because there are important research facilities worldwide. The next are projects with liquid target as a very promising medium. The last part deals with the calculation of basic parameters of ADS in the MCNPX and its applying.
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