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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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Electricity blackout study with regard to the nuclear power plant Dukovany
Žák, Jiří ; Fejta, Libor (referee) ; Radil, Lukáš (advisor)
The entire diploma thesis analyses causes, consequences and repercussions of an electricity grid network blackout and its impact to the respective consumers. Remarkable blackouts recorded since 1965 are briefly described and basic available information is considered. The grid standard fixing measures and electricity delivery priorities are characterized. The thesis also pays attention to entire Czech Republic grid availability and its blackout endurance as well as to its robustness within last several years. Indirect Fukushima event influence to the Czech Republic electricity system is mentioned. The main part of the thesis comprises of four big European grid blackouts causes and consequences, their comparison to each other and to the Dukovany nuclear power plant grid blackout drill scenario. The preventive and standard corrective measures against blackouts are pointed out.
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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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Improving of reliability for NPP
Dubovský, Dávid ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
The aim of this paper is to describe and evaluate the reliability of nuclear plants at Bohunice (EBO). Then illuminate the methods for increasing the reliability and specify one of them (INPO AP 913). After describing the methods, summarize the work results of this method and proposes the way of application.
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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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Evaluation of power and coolant flow in reactor core
Tvrdý, Miloslav ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
This graduation thesis deals with evaluation of power and coolant flow in reactor core. The first part is a description of nuclear power plant VVER 440. It is focused on parts important for transfer and utilize energy in regular operating of generating block. In the second part, the equations for calculation of power and coolant flow in reactor core are deduced. The last part is about designing the program for calculation of published values. There are specified requirements for the program and on the basis of this the source code is written. The parts of code are described. In conclusion of this part, the user's manual is work out. The program is on CD in the annexe.
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Parking house of NPP Dukovany
Okounová, Kateřina ; Rosendorf, Aleš (referee) ; Boleslavská, Yvona (advisor) ; Matějka, Libor (advisor)
The theme of this thesis is the design of two parking houses, which will be made in stages in the area of the Dukovany nuclear power plant. The construction site is located directly in the Dukovany NPP site, south of the cooling towers, which do not interfere with the area in any way. North of this area is a commercial area and bus station, which is separated from the land by buildings and greenery. The five-storey parking houses will not disturb the surrounding character of the buildings. Cooling towers have a big influence on this and they are unmistakable by their height and the designed objects will not have a massive effect next to these towers, they only complement the surrounding buildings. The buildings are designed of regular shape. A more prominent feature on these buildings will be the front facade itself and the glass staircase spaces. The main entrances to the building will be marked with a light sign “P1” and “P2” for better orientation between buildings. The layout of the parking house "S01" in the first stage is designed using two ramps located in the middle of the building. There is also a station for charging electric cars, bicycle storage, sanitary facilities, cleaning room and TZB room. The stairwells are designed in three places for easier access of people. The parking function is complemented in the 1st floor with 6 self-service car wash boxes, which are only accessible from outside the building due to the wet use process. The second stage of construction is considered to be the same layout, the entrance to the second building "S02" is designed from the west side.
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Conceptual design of secondary and tertiary circuit for a new nuclear source
Valíček, Roman ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The aim of this thesis is to create a conceptual design of the secondary and tertiary circuit of a new nuclear power plant in our country, which is preceded by a brief search of particular generations of nuclear reactors. The VVER-1200 reactor became the model for the new nuclear power plant. There was designed a heat diagram containing primary components in this work. After that, there was the balance calculation and calculation of parameters of the main devices of the proposed scheme such as condenser, low-pressure and high-pressure regeneration exchangers and steam generator.
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Calculation of Parameters of Secondary Circuit of Nuclear Power Plant
Vaněček, Lukáš ; Lázničková, Ilona (referee) ; Raček, Jiří (advisor)
The contents of this thesis is a suggestion of calculation and follow-up calculation of parameters of secondary circuit of assigned thermal diagram and parameters of a nuclear power plant. The thesis also includes possibilities of making nuclear circulations. Part one of the thesis briefly describes possibilities of making nuclear circulations, types of nuclear energy reactors, types of steam generators and types of turbines used in nuclear power plants. The second part of the thesis includes a suggestion of calculation for the real thermal diagram of secondary circuit of nuclear power plant. The attention in this calculation is given to expansion of steam in a turbine, determining parameters of mass in a circuit, calculation of steam demanded and determining power and efficiency of nuclear power plant. The final part of the thesis is a calculation of parameters of secondary circuit of nuclear power plant for given values and evaluation of results of calculation.
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