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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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Depletion calculation of VVER 1000 reactor fuel using KENO code
Janošek, Radek ; Katovský, Karel (referee) ; Novotný, Filip (advisor)
The introduction to operational nuclear reactors focusing on light-water pressurized reactor VVER 1000 is in the beginning of this Master´s thesis. This thesis covers basic technology of VVER 1000 reactor with focus on reactor core and nuclear fuel TVSA-T. A significant part of the thesis deal with basic concepts of nuclear safety and its methods. The main goal is to create a model of VVER 1000 reactor, which can be used in nuclear burn-up calculations using KENO code. Therefore a part of this thesis deals with explanation of statistical Monte Carlo method and the KENO code.
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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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Nuclear Fuel Margins Increasing at Nuclear Power Plant Dukovany
Vrábel, Radek ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
This bachelor‘s thesis deals with power uprates and the extension of the nuclear fuel cycle at Czech nuclear power plants. The beginning of this thesis aims at improving the reader’s knowledge about nuclear reactors and nuclear fuel cycle. A whole chapter is dedicated to the development of nuclear fuel cycle at the nuclear power plant Dukovany. The progress in the field of nuclear fuels complements the development of the nuclear fuel cycle, thus providing visible benefits.
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Nuclear energy in Czech republic
Říha, Tomáš ; Bogdálek, Jan (referee) ; Fiedler, Jan (advisor)
The thesis deals with role of nuclear power in the Czech Republic. It analyses the contemporary condition of Czech power plant engineering and predicts its evolution up to the year 2020. It compares possible ways of development and evaluates its viability, political and energy safety and the impact on our environment. The life-prolongation of nuclear power plants and the potential construction of new facilities is taken into consideration. It shows the history of the nuclear power plant engineering in former Czechoslovakia and the problem of nuclear waste is mentioned too. Thesis provides a complex overview of the given topic and emphasizes the subsequent development of the nuclear power plant engineering as the essential part of the power mix.
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Determination of the temperature reactivity coefficient for Nuclear power plant Dukovany
Klíma, Jakub ; Bajgl, Josef (referee) ; Raček, Jiří (advisor)
This thesis deals with the re-determination of the temperature reactivity coefficient of the Nuclear power plant Dukovany, which is measured within the physical test Reheating of the cooling to 260 °C. This paper contains description of the types of nuclear reactors launching, list of tests which are performed during these startings and it also describes methods for determination of temperature reactivity coefficient. Last part of this thesis includes description of programme which was created for determining temperature reactivity coefficient from given files and verification of its calculating methods by statistical test.
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Thermodynamics of the steam cycle of nuclear power plants
Kozák, Tomáš ; Klimeš, Lubomír (referee) ; Štětina, Josef (advisor)
In the first part, the bachelor thesis is focused on derivation of relations that describe thermal cycles. Then, there is an analysis of the ideal Carnot cycle and the Rankine cycle. The ways of increasing the thermodynamic efficiency of Rankine cycle are mentioned, especially the ones that are focused on generating of electricity in nuclear power plants. The second part describes different types of nuclear reactors, their design, the cooling methods and the steam production. The development of the generation IV. nuclear reactors is mentioned at the end of the bachelor thesis.
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Concept of a small nuclear reactor for the heat supply purposes
Bobčík, Marek ; Skála, Zdeněk (referee) ; Martinec, Jiří (advisor)
The objective of this diploma thesis is to assess the suitability of a small nuclear reactor for the purpose of heat supply in small towns and cities. First, all the heat demands of these towns and cities are analysed. Then, a small nuclear reactor to serve these needs is designed and a computational model for burn-up fuel is created. The thesis aims to propose a design of a new heat exchanger. Economic and environmental criteria are taken into account as well and including safety measures. The outcome of this thesis is an evaluation of the whole concept with respect to potential future implementation.
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Effect of a nuclear power plant in terms of radiatin burden
Vániš, Jiří ; Procházka, Zdeněk (referee) ; Belatka, Martin (advisor)
This text deals with ionizing radiation affecting nuclear power plant personnel and surrounding population. Irradiation limits of radiological industry personnel are also mentioned along with ways of protecting them and checks on absorbed ionizing radiation dose. In conclusion, a nuclear power plant, as a source of ionizing radiation, and its effects on contamination of water sources and gas vents are evaluated. The next part be engaged problematical of storage nuclear waste from the time, when is removed the nuclear waste from nuclear reactor, trough permanent storage.
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