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Sodium steam generator for experimental stand
Janíček, Martin ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This thesis deals with the experimental liquid sodium heated steam generator. The first chapters describe the many aspects that should be taken into account when designing this type of steam generator. Furthermore, is approximated in the proposal the work itself. On the basis of thermal, hydraulic calculation of strength and was chosen one preferred option. In conclusion, the best option is evaluated steam generator sodium-water and the possibility of realization.
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Character of nuclear energy in European Union - history and present
Koryčanský, Roman ; Šen, Hugo (referee) ; Martinec, Jiří (advisor)
The thesis deals with the development and current status of nuclear energy in Europe. The first part focuses on the legislative background in the EU – The Euratom treaty. Next, the thesis describes the history of European companies that are engaged in nuclear energy, in particular the French company AREVA. The largest part of the thesis deals with the relationship of nuclear energy and public opinion, and focuses on the status of nuclear energy in selected countries and the attitudes of environmental organizations. This section also includes a description of the history of the most serious accidents. The conclusion focuses on the economic aspects of nuclear energy and its future.
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The flange gasket modification of SG VVER 1000 primary collector
Pransperger, Jan ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This thesis deals with the replacement of the lid gasket of the primary collector of the steam generator VVER 1000. Original sealing by nickel rings is replaced by kammprofile gasket with expanded graphite layers. The thesis compare the properties of both types of gaskets and the new and the original configuration of flange joint which have been calculated according to EN 1591. The results are compared and conclusions arising therefrom are presented. The work includes results of FEM analysis of the new configuration of the flange joint. There is also a description of the main components of the nuclear power plants VVER 1000 primary circuit in the introductory part which focused on the construction and operation of the steam generator and its primary collector.
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Thermal cycles optimization
Voseček, Petr ; Šen, Hugo (referee) ; Fiedler, Jan (advisor)
The main goal of the thesis was a selection of appropriate thermal cycles for the considerated nuclear power stations with the Generation IV reactors. Characterization and specification of the parametres of the Brayton and the Rankine-Clausi thermodynamic cycle, their optimalization with regard to the parametres of the first cycle was made, than analysis of cycles´properties, mostly efficiency, output and process layout.
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Review of world nuclear reactors
Blažková, Eva ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor work is focused on creating an overview of nuclear reactor types, their categorization and engineering approach to particular designs. Furthermore, it also lists countries having nuclear reactors in possession and their standpoint towards nuclear energy in general. A brief summary of the third and fourth generation and their future energy potential is included as well. This work primarily reflects present-day status.
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Fluid flow modeling in rotating engines
Joch, Lukáš ; Šen, Hugo (referee) ; Pospíšil, Jiří (advisor)
This thesis deals with modelling of flow in rotating engines. The introduction of the thesis discusses the principles of CFD modelling, such as mathematical flow model, numerical solution methods and model of turbulence. Next, the thesis is engaged in possibilities of a calculation model creation and its setting for a used model of steam turbine regulatory stage. The last part contains evaluation of calculation models and their comparison with different input parameters, regarding the fact that the aim is to get the most suitable setting for reaching the peak efficiency.
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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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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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Design modification of the collimator for RAW measuring system
Svoboda, Štěpán ; Lisý, Martin (referee) ; Šen, Hugo (advisor)
This thesis deals with structural design of collimator. Collimator is important component of radioactivity measuring device. This apparatus is made by Envinet. Collimator is part of device, which makes good conditions for measuring radioactivity, protects detector and tries avoid overload detector. In this thesis is dealt simplification of collimator. It supposed, that simplified collimator will be more reliable. This proposal saves more money, because company will not have to send employee of Envinet to service their measuring devices in a very distant countries, such as Russia, Ukraine etc.
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The design of components for emergency cooling of reactor pressure vessel
Katzer, Milan ; Šen, Hugo (referee) ; Martinec, Jiří (advisor)
My thesis deals with the design of an experimental emergency cooling device of the reactor pressure vessel (RPV). It consists of two parts, the theoretical one and practical one. Different molten corium cooling methods in terms of their efficiency and comparison are introduced in the theoretical part. The design of an experimental emergency cooling device, which incorporates a model channel past the reactor pressure vessel , is presented in the practical part. The cooling device consists of a model channel past the reactor pressure vessel, condensator, which takes away the heat generated by the reactor pressure vessel and the pump of a secondary loop. Next, thermal and hydraulic calculations are given in this section. The conclusion is devoted to the evaluation of particular cooling technologies and their comparison in terms of nuclear and technical safety.
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