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Software for teaching the control of a nuclear power plant steam generator
Toman, Jiří ; Nekula, Pavel (referee) ; Němec, Zdeněk (advisor)
This diploma thesis deals with the study of steam generator regulation and development of an application, which includes a real simulation of steam generator water level control with its graphical interpretation. It presents analysis and solution in the form of software that will be a valuable application in practice. The result of the diploma thesis is educational software simulating the behavior of the steam generator level control system in referenced nuclear power plant.
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The heat dissipation efficiency of the steam generator Dukovany at low water levels
Veselý, Jakub ; Šnajdárek, Ladislav (referee) ; Pospíšil, Jiří (advisor)
The goal of this thesis is to simulate the course of events during Dukovany Nuclear Power Plant blackout and to determine the optimal process of cooling down the cold branches of the primary circuit loops to secure the maximum amount of the primary fuel needed for the residual heat outlet so that the operating staff has as much time as possible for renewing the electric power supply. The first part of the thesis describes nuclear power plants built in the Czech Republic and in the world as well as reactor blocks whose construction is being considered. The detailed description of Dukovany’s steam generator is shared in chapter three. Following chapter summarizes blackouts that occurred at power plants around the world, events that might have led to blackouts in the Czech Republic, and it also describes current approach to blackout problematics at Dukovany Nuclear Power Plant. Chapters six and seven contain the core of the thesis. That includes detailed description of a mathematical model explaining the behaviour of a reactor block during blackout as well as the analysis of the results found.
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Condenser design of a nuclear power plant
Hejduk, Michal ; Šnajdárek, Ladislav (referee) ; Milčák, Pavel (advisor)
The topic of this master´s thesis is the design of the steam generator for a nuclear power plant with VVER 440 reactor. The first part of this thesis describes a brief history of nuclear research, which is followed by an overview of nuclear reactors used now. The next part deals the types of steam the types of steam generators used today with their basic elements and design recommendations. The last and final part is the design of a steam generator for nuclear power plant with a VVER 440 reactor. Above all, is the thermal calculation of the steam generator and behaviour of steam generator depending on the reactor power. The design solution of steam generator and its strength calculation. The last part of the steam generator calculation the pressure loss of the steam generator is investigated.
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The flange gasket modification of SG VVER 440 primary collector
Blažková, Eva ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to address issues concerning the sealing of the lid for the primary collector within the steam generator (SG) of the nuclear power plant VVER 440. These steam generators are sealed in the original design by nickel rings. Modifying the existing method of sealing by a new type of sealing material, primarily from expanded graphite, can significantly reduce the pressure in the sealing surface and also stress in bolts and flanged joints. The new solution of sealing between the joint of collector and the lid should extend the life of joints and thus the nuclear and technical safety. The text is divided into the theoretical and computational part. A principle of the SG, the SG design, and a description of the joint and lid are mentioned in the theoretical part. The computational part shows calculations of the new joint, the original one, and comparison of both solutions in terms of technical and nuclear safety. The work contains drawing of the new joint.
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Upgrading the secondary circuit of the Dukovany NPP
Fialová, Michaela ; Fiedler, Jan (referee) ; Šen, Hugo (advisor)
With the ever increasing usage of electric power and decreasing supply of natural resources, there is a growing effort to effectivelly maximise current dispositions of resources. Utilising project reserves at already functioning Nuclear powerplants belongs to these projects. In this article I am going to describe this utilisation and overall modernisation of the Dukovany Nuclear powerplant.
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The feedwater safety valve flow capacity analysis
Fialová, Michaela ; Lisý, Martin (referee) ; Šen, Hugo (advisor)
In this thesis I review the sufficient flow capacity of the safety valve against high-pressure heater thermal pressurization in high-pressure feedwater heater on nuclear power Dukovany. I present basic possible cases of thermal pressurization both a high node heater, and the extended pressure unit in case of closure all power heads to steam generators.
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Analysis of the secondary circuit of the VVER 440 block
Černý, Michal ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The main aim of this thesis is the model design and control the secondary circuit block VVER 440. The search part of my work is a description of the secondary circuit. In the first part of the calculation is performed for the rated secondary circuit. The second calculation part focuses on the calculation circuit of the secondary for the reduced, influenced by shutting down one steam generator.
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Expressing uncertainty of efficiency value
Kňava, Miroslav ; Pernikář, Jiří (referee) ; Koška, Petr (advisor)
The aim of this work is to analyze the methodology for executing examination heat transfer tubes of steam generator by method of eddy currents on EDU, to create the model for the estimate of standard combined uncertainty of efficiency value, quantify the individual components of standard uncertainties, analyse the influence of different components on the expressing of uncertainty, to make the final estimate of standard combined and enlarged uncertainty of efficiency value and as of minor objective to evaluate the suitability of the use of this method .
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Repair TS tubes of the steam generator by manual welding
Zeman, Tomáš ; Mrňa, Libor (referee) ; Kubíček, Jaroslav (advisor)
This bachelor thesis deals with repair of heat exchange tubes of steam generator of Dukovany Nuclear Power Plant. Defects in the material of the collector of the steam generator were to such an extent that it was necessary to proceed with manual repair by workers inside the collector. A number of inspection welds, thorough training and preparation were performed to obtain the qualification of the repair. The repair was followed by a series of tests and trials, which ended in a satisfactory result and the equipment was put into operation.
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