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Nuclear power before and after the disaster of Fukushima Daiichi
Hanuš, Jan ; Moskalík, Jiří (referee) ; Martinec, Jiří (advisor)
This bachelor’s thesis is written about accident in Fukushima Daiichi power plant. There are described causes and consequences of this accident and also status of nuclear energy before and after this accident. The disaster at Fukushima Daiichi is compared with the disaster at Cernobyl nuclear power plant in this work too. At the end of this thesis is written technical and economical study for phase out of nuclear energy in the Czech Republic.
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The concept of the heat exchanger for the IMSR reactor
Števanka, Kamil ; Katovský, Karel (referee) ; Martinec, Jiří (advisor)
Cílem práce bylo vytvořit základní koncept integrovaného výměníku tepla pro solí chlazený reaktor vyvíjený společností Terrestrial Energy s využitím programu Promex. První kapitola se zabývá historií a současnou situací v oblasti výzkumu malých modulárních reaktorů chlazených fluoridovými solemi. Ve druhé kapitole jsou popsány vlastnosti fluoridových solí a konstrukčních materiálů. Poslední kapitola se zabývá simulací tepelného výměníku pomocí programu Promex, validací modelu, transformací protiproudého výměníku na výměník s U trubkami a vizualizací výměníku s použitím CAD Invetoru.
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Engineering design of the Freeze Valve
Zeman, Radek ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This bachelor´s thesis deals with practical design of freeze valve for nuclear facilities from both calculation and construction point of view. Firstly, a brief analysis of technologies of fast neutron reactors and reactors with fuel dissolved in melted fluorine salts has been done. The author points out the advantages of their use that may result in becoming an important part of nuclear power engineering. Working fluids are taken from these reactors – liquid sodium and mixture of molten salts NaBF4-NaF. The author deals with choice of suitable construction materials and ways of heat-transfer from working fluid. Secondly, several construction solutions have been assessed and project documentation has been created for some of them. These designs include alternative shapes of valves and canals, where heat exchanging medium flows – Field tube and valve with helix canal. These concepts allow fast intake (conducting away) of heat into the working fluid and after verification on an experimental stand these valves could work in conditions of nuclear facilities. Times of cooling and heating for chosen designs and working fluids are calculated by previously derived dimensionless equations describing transient heat-transfer field with phase change supposing low Biot numbers.
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Modernization the Dukovany Nuclear Power Station
Kissler, Martin ; Martinec, Jiří (referee) ; Fiedler, Jan (advisor)
Thesis focuses on a detailed technical description of all important parts of secondary circuit in Dukovany power plant and its connection to other systems of power plant. In thesis are analyzed significant adjustments which have been made during the entire operation of power plant including in particular the actions associated with project called Utilization of project reserves of units EDU. In the main part of the thesis were carried out calculations of the power plant's power for states before and after the modernization and there is also analyzed the impact of individual changes on the whole power plant. These changes are with the entire secondary circuit drawn in the T-s diagram.
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Condensing Steam Turbine
Kracík, Petr ; Martinec, Jiří (referee) ; Fiedler, Jan (advisor)
Diploma thesis named Condensing steam turbine deals with heat scheme balancing computation of condensing steam turbine K55 and her design. This turbine with 5 unregulated take-offs and overpressure blading type, is computed with (c_a/u) method in the middle of blading diameter. Regulation degree is chosen with impulse blading and feet cross section is checked on durability. At the end of the thesis turbine consumption characteristic is derived from the zero output up to the nominal output. Integrated part of this thesis is conceptional design of longitudal turbine section.
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The concept of the heat exchanger for the IMSR reactor
Števanka, Kamil ; Katovský, Karel (referee) ; Martinec, Jiří (advisor)
Cílem práce bylo vytvořit základní koncept integrovaného výměníku tepla pro solí chlazený reaktor vyvíjený společností Terrestrial Energy s využitím programu Promex. První kapitola se zabývá historií a současnou situací v oblasti výzkumu malých modulárních reaktorů chlazených fluoridovými solemi. Ve druhé kapitole jsou popsány vlastnosti fluoridových solí a konstrukčních materiálů. Poslední kapitola se zabývá simulací tepelného výměníku pomocí programu Promex, validací modelu, transformací protiproudého výměníku na výměník s U trubkami a vizualizací výměníku s použitím CAD Invetoru.
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The concept for passive cooling of the VVER-1000 reactor
Lamoš, Pavel ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis is focused on the design of passive cooling system for a nuclear reactor VVER- 1000.This type of reactor is located in the Czech Republic in the location of Nuclear power plant Temelín. The thesis states an overview of the different cooling systems of nuclear power plants. The thesis is focused on passive safety system especially on passive cooling system, so there was done an overview of currently used passive safety system. In the work is discussed nuclear safety and the maximum projected accident of VVER-1000, which is called LOCA accident. In the design part of the thesis was done thermal calculation of heat exchangers. Exchangers are designed as condensers with a natural flow, where cooling of system is provided by outside airflow in case an accident. The results are evaluated at the end of the thesis.
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