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Technology of increasing the efficiency of nuclear power plants
Poláková, Barbora ; Imrichová, Anna (referee) ; Milčák, Pavel (advisor)
This bachelor thesis deals with increasing the efficiency of nuclear power plants, specifically the design of a steam heater. The introduction is devoted to nuclear energy in general, its history, the principle of energy extraction and new nuclear sources in the Czech Republic. The second part focuses on the analysis of the Dukovany nuclear power plant and the possibilities of increasing its efficiency. The third part describes in detail the steam separation and heating technology and its influence on efficiency. In the last two chapters is resented the thermodynamic analysis and the design of the heat exchanger, the aim of which was to determine its length and heat transfer surface.
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Boiler with steam reheating for burning blast furnace gas
Šenovský, Petr ; Lisý, Martin (referee) ; Baláš, Marek (advisor)
The aim of this Diploma thesis is design of steam boiler with steam reheating, for combustion the blast furnace gas. The fuel composition and primary parameters for calculation of the boiler were provided. In the first part the fuel composition is described. The main part of the thesis consists of stoichiometric calculations, establishing efficiency of the boiler, calculating combustion chamber as well as design and calculation individual heating surfaces. Part of the work is also drawing documentation of boiler.
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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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Boiler with steam reheating for burning blast furnace gas
Šenovský, Petr ; Lisý, Martin (referee) ; Baláš, Marek (advisor)
The aim of this Diploma thesis is design of steam boiler with steam reheating, for combustion the blast furnace gas. The fuel composition and primary parameters for calculation of the boiler were provided. In the first part the fuel composition is described. The main part of the thesis consists of stoichiometric calculations, establishing efficiency of the boiler, calculating combustion chamber as well as design and calculation individual heating surfaces. Part of the work is also drawing documentation of boiler.
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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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