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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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Steam Generators of PWR
Michalica, Martin ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
This bachelors thesis describes various designs of steam generators. The first part of the thesis describes the beginning of the nuclear industry in Russia. The main part deals with individual design solutions. The last chapter describes in detail the various parts of the steam generator VVER 1000. The work includes creation of a 3D model of the steam generator VVER 1000, which will serve as a teaching aid in the project Cenelín.
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Design of the steam generator for a nuclear power plant
Hort, Lukáš ; Špiláček, Michal (referee) ; Milčák, Pavel (advisor)
This bachelor's thesis is about the design of a steam generator for a nuclear power plant. The opening chapters are purely theoretical, with the first one covering nuclear energy as such, the next one continuing with the search for different types of parogenerators and their subsequent comparison. This is followed by a calculation section dealing with the thermal calculation of the parogenerator for the given parameters.
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Energy conversion systems for nuclear power plants with soduim fast reactor (SFR)
Netopilová, Petra ; Šen, Hugo (referee) ; Matal, Oldřich (advisor)
The aim of the dissertation is proposing and solving energy convection systems for nuc-lear power plants with a sodium fast reactor of the 4th generation. The first part of the dissertation deals with collection and evaluation of information available about nuclear power plants with sodium fast reactor which use nuclear or non-nuclear reheating to increase thermal efficiency. On the basis of the acquired information, thermal schemes are developed and thermal effi-ciency is determined for the systems working in both Rankine thermal cycle and Brayton thermal cycle. In the further part of the dissertation thermal calculation of the reheater for nuclear and non-nuclear reheating is made for the systems working in Rankine thermal cycle. At the end of this dissertation, an apparatus suitable for these systems is suggested and the systems are evaluated in terms of technical implementation and nuclear safety.
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Design of Steam Generator 13 t/h
Pálka, Jaroslav ; Kraml, Stanislav (referee) ; Lisý, Martin (advisor)
Master's thesis focuses on the design of a steam generator that utilizes superheated steam from a woodchip boiler for heating purposes. The steam generator produces saturated steam with variable parameters that depend on operational requirements. The integration of the steam generator into the thermal circuit is also taken into consideration. The primary objective of this thesis is to conduct through thermal calculations for the steam generator and design the inlets and outlets. In addition, a basic process control system has been designed.
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The design of nuclear power plant steam generator
Zimmermann, Jakub ; Baláš, Marek (referee) ; Milčák, Pavel (advisor)
The bachelor's thesis consists of three parts. The introductory research section briefly describes the history of nuclear energy, followed by an analysis of the three circuits (primary, secondary, and tertiary) in a nuclear power plant. The second part provides a detailed description of various steam generators used worldwide. The third and main part of this bachelor's thesis covers the thermal calculation of a steam generator, focusing on determining the heat exchange surface area and the length of heat exchange tubes inside, followed by a comparison of steam generator sizes based on their number of connections to a single nuclear reactor block. At the end, I modelled a model and created a diagram of the steam generator based on the results from the thermal calculation.
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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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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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Design of the steam generator for a nuclear power plant
Hort, Lukáš ; Špiláček, Michal (referee) ; Milčák, Pavel (advisor)
This bachelor's thesis is about the design of a steam generator for a nuclear power plant. The opening chapters are purely theoretical, with the first one covering nuclear energy as such, the next one continuing with the search for different types of parogenerators and their subsequent comparison. This is followed by a calculation section dealing with the thermal calculation of the parogenerator for the given parameters.
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